НЕЙТРОННЫЙ ЗАЩИТНЫЙ ЭКРАН ПОВЫШЕННОЙ ПРОЧНОСТИ

Изобретение относится в основном к устройствам радиационной защиты, в частности к радиационным защитным экранам для подземного оборудования. В составе защитного экрана для аппаратуры геофизических исследований в скважинах (каротажа) имеется внешний слой, в который включено армирующее волокно, помещенное в матрицу, и внутренний слой, содержащий материал, способный поглощать тепловые нейтроны и внедренный в матрицу. Материал, способный поглощать тепловые нейтроны, подобран так, чтобы он испускал захватное гамма-излучение с энергией вне выбранного диапазона энергий. Технический результат - обеспечение необходимой защиты от радиации и/или ее поглощение. 2 н. и 15 з.п. ф-лы, 5 ил.

СПОСОБ ОПРЕДЕЛЕНИЯ ЧИСЛА ДЕЛЕНИЙ В ИМПУЛЬСНОМ ПРОЦЕССЕ ДЕЛЕНИЯ

Использование: изобретение относится к области экспериментальной ядерной физики, конкретно к методам регистрации импульсных процессов деления, и может быть использовано для определения числа делений, происходящих в импульсном источнике нейтронов деления. Сущность: производят регистрацию временного распределения запаздывающей части нейтронного импульса, определяют число зарегистрированных запаздывающих нейтронов и используют найденное число запаздывающих нейтронов при определении числа делений. Техническим результатом является расширение диапазона регистрации числа делений и устранение неопределенности, связанной с вкладом нейтронов инициирующего нейтронного генератора в результат измерений. 3 ил.

СПОСОБ ИЗМЕРЕНИЯ АСИММЕТРИИ РАСПАДА ПОЛЯРИЗОВАННЫХ ПУЧКОВ

Изобретение относится к области ядерной физики. Способ измерения асимметрии распада поляризованных пучков включает в себя пропускание поляризованного пучка частиц через контролируемую зону, регистрацию заряженных частиц, испускаемых асимметрично относительно спина распадающихся частиц, контрольные измерения при изменении направления поляризации пучка на 180°, при этом исходный поляризованный пучок частиц пропускают через зону контроля с близким к нулю магнитным полем, поток частиц исходного поляризованного пучка ступенчато варьируют с помощью прецизионной управляемой диафрагмы, на каждой ступени потока проводят многократные измерения скорости счета и энергетического спектра испускаемых в зоне контроля заряженных частиц с помощью охватывающего пучок секционированного по углу детектора; по совокупности скоростей счета и их погрешностей строят функционал ошибок для оценок чисел частиц в зоне видимости детектора путем приближений этих чисел шкалой (последовательностью) с шагом 1/μ, значение ...

СПОСОБ ДЛЯ ОПРЕДЕЛЕНИЯ НАПРАВЛЕННОСТИ РАДИОАКТИВНОГО ИЗЛУЧЕНИЯ И УСТРОЙСТВО ДЛЯ ЕГО ОСУЩЕСТВЛЕНИЯ

Изобретение относится к способам определения направленности радиоактивного излучения. Способ определения направленности радиоактивного излучения включает создание объема метастабильной протянутой текучей среды; размещение объема метастабильной протянутой текучей среды в непосредственной близости от источника радиоактивного излучения; определение положения кавитаций, вызванных радиоактивным излучением, в метастабильной протянутой текучей среде; и определение направления источника радиоактивного излучения на основании кавитаций, вызванных радиоактивным излучением, в метастабильной протянутой текучей среде. Устройство для определения направленности падающего радиоактивного излучения содержит камеру, содержащую текучую среду, систему управления, связанную с механизмом для деформации камеры, которые совместно функционируют для создания и поддержания в текучей среде напряженного метастабильного состояния, достаточного для формирования кавитационных пузырьков при столкновениях молекул текучей ...

СПОСОБ ИЗМЕРЕНИЯ ВЫХОДА НЕЙТРОНОВ

Использование: для регистрации и контроля выхода нейтронов импульсного источника типа нейтронного генератора. Сущность: способ измерения выхода нейтронов импульсного источника основан на измерении одним регистрационным каналом двух активационных детекторов с различным периодом полураспада в течение двух заданных промежутков времени после прихода нейтронного импульса, причем задержку между заданными промежутками времени выбирают из условия получения экстремума производной отношения С2 /С1 в зависимости от задержки заданных промежутков времени относительно прихода нейтронного импульса, а длительность второго промежутка времени выбирают из соотношения t2 = t1λ1/λ2, При этом измерение активности за каждый промежуток времени проводят в двух соответствующих подынтервалах, причем по отношению С11/С12 контролируют значение первого промежутка времени, а по отношению С23 /С24 контролируют второй промежуток времени, а длительности подынтервалов второго промежутка времени выбирают пропорционально длительности ...

УСТРОЙСТВО ДЛЯ ДЕТЕКТИРОВАНИЯ И СПЕКТРОМЕТРИИ НЕЙТРОНОВ

Использование: для определения энергетического распределения направленного нейтронного излучения в диапазоне энергий нейтронов от тепловых до быстрых. Устройство содержит единый блок из замедлителя нейтронов, группы датчиков тепловых и медленных нейтронов и счетчики электрических импульсов от каждой группы датчиков. Каждая группа датчиков расположена внутри блока замедлителя на расстоянии от фронтальной поверхности, равном средней длине замедления нейтронов данной регистрируемой энергетической группы. Датчики нейтронов размещены в плоскости каждой группы на расстоянии друг от друга порядка или менее длины релаксации медленных нейтронов в материале замедлителя. Датчики каждой группы относительно датчиков соседних групп расположены так, что перекрытие геометрических проекций датчиков соседних групп на плоскость, перпендикулярную направлению излучения, минимально. Детектирующее устройство со всех сторон, кроме фронтальной, окружено слоем замедляющего и поглощающего нейтроны материала. Технический ...

ЛИНЕЙНО-ЛОГАРИФМИЧЕСКИЙ ИЗМЕРИТЕЛЬ ПОТОКА НЕЙТРОНОВ С САМОНАСТРАИВАЮЩИМСЯ ФИЛЬТРОМ

Устройство для измерения потока нейтронов в реакторе в режиме пуска, состоящее из одной ионизационной камеры и одного операционного усилителя, отличающееся тем, что для расширения диапазона измерения на малых и больших уровнях мощности в его цепь обратной связи последовательно включены логарифмический диод D и резистор R, а с целью изменения степени фильтрации на различных уровнях мощности параллельно с ними включен конденсатор C, который придает устройству свойства самонастраивающегося фильтра.

УСТРОЙСТВО ДЛЯ ФОРМИРОВАНИЯ МОНОЭНЕРГЕТИЧЕСКИХ НЕЙТРОННЫХ ПУЧКОВ НИЗКИХ ЭНЕРГИЙ

Устройство для формирования моноэнергетических нейтронных пучков низких энергий, включающее камеру удержания ультрахолодных нейтронов с входным и выходным отверстиями, установленное с возможностью перемещения внутри камеры удержания средство взаимодействия с нейтронами, включающее полиэтиленовый элемент, отличающееся тем, что оно дополнительно снабжено подключенным к выходному отверстию камеры удержания выводящим нейтроны каналом, имеющим выходное окно из алюминиевой фольги, средство взаимодействия с нейтронами выполнено в виде полиэтиленового диска-поглотителя, дно камеры удержания ультрахолодных нейтронов выполнено с искусственной макрошероховатостью поверхности, стенки камеры удержания ультрахолодных нейтронов и стенки выводящего нейтроны канала покрыты жидким фторополимером.

ДВУХКООРДИНАТНЫЙ ПОЗИЦИОННО-ЧУВСТВИТЕЛЬНЫЙ ДЕТЕКТОР ТЕПЛОВЫХ И ХОЛОДНЫХ НЕЙТРОНОВ

Полезная модель относится к области регистрации и измерения ядерных излучений и предназначена для исследования с помощью тепловых и холодных нейтронов структуры вещества. Двухкоординатный позиционно-чувствительный детектор тепловых и холодных нейтронов состоит из герметичного корпуса, заполненного газовой смесью, например Ar(80%)/CO(20%), при атмосферном давлении на продув, системы электродов - катода и анода, составляющих ячейки, размещенные с определенным шагом и объединенные в первый детектирующий слой. Катодом ячейки служит пластинка-подложка из алюминия с нанесенной на ее поверхность тонкой пленкой карбида бораBC, обогащенного до 80% изотопомB, а анодом - тонкие вольфрамовые проволочки, размещенные между пластинками, причем пластинки повернуты на небольшой угол относительно нормали к поверхности входного окна детектора. Введен идентичный первому второй детектирующий слой с углом поворота пластинок, измененным на противоположный, с образованием шевронной структуры, при этом пластинки ...

СПОСОБ РЕГИСТРАЦИИ НЕЙТРОНОВ В ПРИСУТСТВИИ ГАММА-ИЗЛУЧЕНИЯ

Изобретение относится к области приборостроения и может найти применение при измерении плотности потока нейтронов в присутствии других видов излучений. Технический результат - расширение функциональных возможностей. Для достижения данного результата значения мощности экспозиционной дозы гамма-излучения постоянно контролируют самим детектором нейтронов. При этом осуществляют измерения постоянного тока Iγ, возникающего в детекторе нейтронов под действием гамма-излучения, значения которого используют: для определения и установки такого порога дискриминации, который обеспечивает максимальную эффективность детектора при мощности экспозиционной дозы гамма-излучения, имеющей место в текущем цикле измерений; для определения степени снижения относительной эффективности детектора под действием гамма-излучения и приведения ее к максимально возможной; для определения мощности экспозиционной дозы гамма-излучения. 1 з.п. ф-лы, 6 ил.

ПОЗИЦИОННО-ЧУВСТВИТЕЛЬНЫЙ ДЕТЕКТОР ТЕПЛОВЫХ НЕЙТРОНОВ

... 1. Позиционно-чувствительный детектор тепловых нейтронов, включающий: герметичный корпус, с элементами поддержки электродов, наполненный газовой смесью, входное окно, центральный проволочный анодный электрод, два проволочных катодных координатных электрода, расположенные симметрично по обе стороны от центрального анодного электрода с некоторым зазором, два проволочных катодных дрейфовых электрода, расположенных за ними подобным образом, причем проволочки каждого катодного координатного электрода соединены в стрипы и ориентированы взаимно перпендикулярно относительно друг друга для получения декартовых координат Χ, Y и эти стрипы подключены к своим линиям задержки, отличающийся тем, что между катодным дрейфовым электродом и катодным координатным электродом в дрейфовом зазоре расположен материал пористой структуры из аэрогеля: различные типы материала Pyrogel, толщиной, например, 5-10 мм, обогащенный одним из изотопов, который эффективно захватывает нейтрон и вступает с ним в ядерное взаимодействие ...

ГАЗОВЫЙ СЧЕТЧИК МЕДЛЕННЫХ НЕЙТРОНОВ

Газовый счетчик медленных нейтронов, содержащий цилиндрический корпус с центральным электродом в виде нити и нейтронный радиатор, нанесенный на внутреннюю поверхность корпуса в виде твердого соединения бора, обогащенного изотопомВ до 85 %, электрические выводы и изоляторы у торцов корпуса, отличающийся тем, что счетчик заполнен смесьюНе+3 % Аr с давлением 1 атм.

СЦИНТИЛЛЯЦИОННЫЙ МАТЕРИАЛ ДЛЯ РЕГИСТРАЦИИ ИОНИЗИРУЮЩЕГО ИЗЛУЧЕНИЯ (ВАРИАНТЫ)

Группа изобретений относится к материалам, используемым в сцинтилляционной технике. Сущность группы изобретений заключается в том, что сцинтилляционный материал для регистрации ионизирующего излучения представляет собой кристаллический твердый раствор с общей эмпирической формулой Li(YLu)Fпри х=0,01-0,8, образующийся в бинарной системе LiYF- LiLuF. Также сцинтилляционный материал для регистрации ионизирующего излучения представляет собой кристаллический твердый раствор с общей эмпирической формулой Ba(YYb)Fпри х=0,01-0,9, образующийся в бинарной системе BaYF- BaYbF. Технический результат – получение сцинтилляционных материалов, в том числе крупногабаритных, с возможностью направленного управления чувствительностью данных материалов к ионизирующим излучениям с максимальной чувствительностью к излучению γ-квантов. 2 н. и 9 з.п. ф-лы, 1 ил.

ИОНИЗАЦИОННАЯ КАМЕРА ДЕЛЕНИЯ

Использование: для исследования и контроля работы реакторных установок различного типа. Сущность изобретения: в ионизационной камере деления электрод компенсационной секции камеры имеет с двух сторон радиатор из ураносодержащего вещества и фильтр, электрически соединенный с электродом. Радиатор компенсационной камеры содержит количество урана в (1+ε) большее, чем радиатор в рабочей секции, где ε - относительное поглощение бета-излучения продуктов давления при прохождении его через фильтр. Толщина фильтра равна максимальной величине пробега осколков в нем. Фильтр выполнен из электропроводного материала, имеющего малое сечение активации. 1 ил.

СПОСОБ РЕГИСТРАЦИИ МЕДЛЕННЫХ И БЫСТРЫХ НЕЙТРОНОВ В УСЛОВИЯХ ИНТЕНСИВНОЙ ВНЕШНЕЙ РАДИАЦИИ

Изобретение относится к детекторам элементарных частиц и может быть применено для регистрации нейтронов в физических экспериментах, а также в атомной энергетики (в зонах АЭС, в которых имеется интенсивное гамма-излучение). Технический результат - возможность функционирования детектора нейтронов в условиях рекордно интенсивного гамма-фона (до 100 рад/ч), использование более простой и быстрой электроники для регистрации нейтронов и режекции сигналов от фоновых электронов как по амплитуде, так и по форме импульсов, возможность увеличения регистрации нейтронов (скорости счета). Способ регистрации медленных и быстрых нейтронов в условиях интенсивной внешней радиации, характеризующийся направлением пучка нейтронов в детектор, содержащий корпус в виде цилиндрической трубки, которую заполняют газом, внутри которой посередине располагают анод, а по контуру трубки катод, подключенный к линии высокого напряжения, и отделяющий катод от корпуса изолятор, отличающийся тем, что пучок нейтронов пропускают ...

СПОСОБ ИЗМЕРЕНИЯ МОЩНОСТИ ДОЗЫ В ТКАНЕЭКВИВАЛЕНТНОМ МАТЕРИАЛЕ ПРИ ГАММА-НЕЙТРОННОМ ОБЛУЧЕНИИ

Использование: в дозиметрии при гамма-нейтронном облучении, точнее при определении мощности дозы, поглощенной фантомом. Сущность изобретения: способ измерения мощности дозы в тканеэквивалентном материале при гамма-нейтронном облучении заключается в том, что на электроды твердотельной ионизационной камеры, межэлектродный промежуток в которой заполнен водородсодержащим диэлектриком, подают электрическое напряжение питания, облучают импульсом гамма-нейтронного излучения и измеряют временную зависимость сигнала с двумя максимумами, по которому судят о мощности дозы, поглощенной в тканеэквивалентном материале, одновременно измеряют временную зависимость сигнала детектора быстрых нейтронов, выделяют составляющие сигнала, максимум первого из которых опережает, а максимум второго совпадает с максимумом импульса излучения, по значению первого составляющего сигнала на переднем фронте в интервале времени, в котором временная зависимость сигнала пропорциональна временной зависимости сигнала детектора ...

УСТРОЙСТВО ДЛЯ РЕГИСТРАЦИИ ПОТОКОВ НЕЙТРОНОВ

Использование: определение энергетического распределения направленных потоков нейтронов в диапазоне энергий от тепловых до 20 МэВ. Сущность изобретения: устройство для регистрации потоков нейтронов содержит мишень, состоящую из замедляющих нейтроны слоев, чередующихся в направлении градиента нейтронного потока со слоями регистраторов тепловых и медленных нейтронов, в качестве которых использованы газоразрядные счетчики нейтронов, расположенные равномерно в каждом слое. Каждый слой счетчиков подключен к соответствующему счетчику электрических импульсов электронного блока. 2 ил.

УСТРОЙСТВО ДЛЯ ИЗМЕРЕНИЯ ПОТОКА НЕЙТРОНОВ

Изобретение относится к области измерения излучений. Устройство для измерения потока нейтронов содержит первичный преобразователь в виде ионизационной двухсекционной трехэлектродной камеры, к общесекционному электроду которой подключен однополярный источник питания, а к разнополярным электродам, к положительному, входящему в состав нейтронной секции, и к отрицательному, входящему в состав компенсационной секции, - блоки измерения тока, которые связаны с блоком обработки выходных сигналов, при этом блоки измерения тока состоят из преобразователя ток-напряжение, выполненного на основе линейного усилителя с переключающимися пределами измерения или на основе логарифмического усилителя, выход которого подключен к входу аналого-цифрового преобразователя, управляемого микроконтроллером, выход которого через интерфейс связи подключен к интерфейсу связи блока обработки выходных сигналов, который имеет возможность подключения к вычислительному устройству более высокого уровня и включает в себя свой ...

СПОСОБ И УСТРОЙСТВО ДЛЯ ИЗМЕРЕНИЯ ПРОФИЛЯ НЕЙТРОННОГО ПУЧКА (ПУЧКОВ)

Изобретение относится к области радиационных технологий, а также к исследованиям, созданию и эксплуатации ядерных установок и ускорителей. Способ измерения профиля нейтронного пучка (пучков) в плоскости, перпендикулярной выделенному его (их) направлению, заключается в том, что пучок (пучки) быстрых нейтронов направляют на детектирующую плоскость профилометра, перпендикулярно расположенную к его (их) направлению (направлениям), поверхность которой представляет собой совокупность параллельно расположенных изолированных стрипов, сигналы с каждого из стрипов, появившиеся в результате взаимодействия нейтрона с веществом стрипа, поступают на блок регистрирующей электроники, производящей прием и анализ зарегистрированных событий с использованием программного обеспечения для определения профиля нейтронного пучка (пучков), при этом в качестве детектирующей плоскости профилометра используют двусторонний стриповый кремниевый детектор, одна сторона которого представляет набор X-стрипов, а вторая - ...

НЕЙТРОННЫЙ ЗАЩИТНЫЙ ЭКРАН ПОВЫШЕННОЙ ПРОЧНОСТИ

... 1. Защитный экран для аппаратуры каротажа скважины, содержащий: ! - внешний слой, включающий армирующее волокно, помещенное в матрицу, ! - внутренний слой, содержащий материал, способный поглощать тепловые нейтроны, помещенный в матрицу; причем материал, способный поглощать тепловые нейтроны, подобран так, чтобы он испускал захватное гамма-излучение с энергией вне заданного диапазона энергий гамма-излучения, представляющего интерес как диапазон энергий гамма-лучей, испускаемых вследствие взаимодействия нейтронов с породой. ! 2. Защитный экран по п.1, в котором материал, поглощающий тепловые нейтроны, содержит бор-10. ! 3. Защитный экран по п.1, в котором матрица внешнего слоя содержит по меньшей мере одно из следующих веществ: нитриловый каучук, полиэфиркетон, полиэфирэфиркетон, полиэфиркетон-кетон. ! 4. Защитный экран по п.1, в котором армирующее волокно содержит по меньшей мере один из следующих материалов: стекловолокно либо углеродное волокно. ! 5. Защитный экран по п.1, в котором материал ...

УСТРОЙСТВО ДЛЯ ОПРЕДЕЛЕНИЯ ЭНЕРГЕТИЧЕСКОГО РАСПРЕДЕЛЕНИЯ УЛЬТРАХОЛОДНЫХ НЕЙТРОНОВ, НАКОПЛЕННЫХ В СОСУДЕ

... 1. Устройство для определения энергетического распределения ультрахолодных нейтронов, накопленных в сосуде, содержащее сосуд хранения, снабженный входным и выходным патрубками с заслонками и запирающей заслонкой, детектор ультрахолодных нейтронов, присоединенный к выходному патрубку, и шток, введенный внутрь сосуда, отличающееся тем, что, с целью повышения точности определения энергетического распределения нейтронов, устройство снабжено детектором тепловых нейтронов, помещенным внутри сосуда хранения и заключенным в контейнер, на котором установлен нагреватель ультрахолодных нейтронов, причем контейнер соединен со штоком. 2. Устройство по п. 1, отличающееся тем, что в качестве нагревателя ультрахолодных нейтронов использован слой полиэтилена.

УСТРОЙСТВО ДЛЯ ОПРЕДЕЛЕНИЯ РАССТОЯНИЯ ДО ИСТОЧНИКА НЕЙТРОНОВ

Изобретение относится к области поиска и обнаружения радиоактивных источников, в частности источников нейтронного излучения. Целью изобретения является снижение трудоемкости определения расстояния до источника нейтронов и обеспечение измерения расстояния до источника в труднодоступных местах. Устройство для определения расстояния до источника нейтронов содержит сборку счетчиков тепловых нейтронов, установленную внутри плоского замедлителя параллельно его передней и задней поверхности, и регистрирующее устройство. Замедлитель выполнен разъемным с возможностью удаления ближайшей к источнику нейтронов части замедлителя, причем отношение толщины ближней к источнику части замедлителя к толщине дальней равно 1:2. Изобретение позволяет определять расстояние до источника нейтронов в пределах 5-50 м, давать нижнюю оценку расстояния при расположении источника дальше 50 м. При этом измерения проводятся в одной точке, без смещения устройства. 4 ил.

УСТРОЙСТВО ДЛЯ РЕГИСТРАЦИИ НЕЙТРОНОВ

... 1. Устройство для регистрации нейтронов с наиболее вероятной энергией 250 кэВ, содержащее радиатор из вещества, обогащенного литием-6, и 1/V - детекторы, помещенные в борный фильтр толщиной 2 г/см2 с оболочкой из лития-7, отличающееся тем, что, с целью повышения чувствительности к нейтронам в резонансной области сечения лития-6 и точности определения потока нейтронов, в нем 1/V - детекторы выполнены в виде плоских радиаторов из бора-10 и дополнительно установлены трековые детекторы α-частиц, расположенные с обеих сторон каждого радиатора. 2. Устройство по п.1, отличающееся тем, что литиевые и борные радиаторы выполнены в виде нескольких пластин различной толщины, одна из которых имеет толщину, равную пробегу α-частиц в радиаторе, а каждая из последующих - в 103 раз меньшую.

УСТРОЙСТВО КАНАЛА ДЛЯ ИЗМЕРЕНИЯ ПОТОКА НЕЙТРОНОВ

Использование: при измерении потока нейтронов первичным преобразователем на основе блока ионизационных камер в системе управления и защиты ядерного реактора, критической сборки и других источников нейтронов. Сущность изобретения: устройство канала для измерения потока нейтронов состоит из первичного преобразователя, содержащего два нейтроночувствительных объема с электрически изолированными сигнальными электродами, в которых помещен материал с количеством ядер nи n Подробнее

УСТРОЙСТВО ДЛЯ РЕГИСТРАЦИИ ПОТОКОВ НЕЙТРОНОВ

Изобретение относится к области технической физики и может быть использовано для определения энергетического распределения направленных потоков нейтронов в диапазоне энергий от тепловых до 20 МэВ. Сущность предполагаемого изобретения заключается в том, что в устройстве для регистрации потоков нейтронов, содержащем мишень, состоящую из замедляющих и поглощающих нейтроны слоев, чередующихся в направлении градиента нейтронного потоками, электронный блок, состоящий из счетчиков электрических импульсов, поглощающие нейтроны слои представляют слои регистраторов тепловых и медленных нейтронов, в качестве которых применены газоразрядные счетчики нейтронов, расположенные равномерно в каждом поглощающем слое, причем каждый слой подключен к соответствующему счетчику электрических импульсов электронного блока. Устройство позволяет определить энергетическое распределение направленных потоков нейтронов и обладает значительно большей эффективностью регистрации нейтронов и значительно большей чувствительностью ...

УСТРОЙСТВО ДЕТЕКТИРОВАНИЯ ШИРОКОДИАПАЗОННЫХ КАНАЛОВ КОНТРОЛЯ НЕЙТРОННОГО ПОТОКА

Устройство детектирования широкодиапазонных каналов контроля нейтронного потока, содержащее ионизационные камеры деления, усилители, линейные амплитудные дискриминаторы, логарифмические преобразователи импульсных и средних токов, источник высокого напряжения, отличающееся тем, что в него введен блок микроконтроллера, содержащий электронный коммутатор, аналого-цифровой преобразователь, цифровой сигнальный процессор, запоминающее устройство, приемопередатчик, первый и второй цифроаналоговые преобразователи, при этом входы электронного коммутатора соединены с выходами логарифмических преобразователей импульсного и среднего тока, а его выход соединен со входом аналого-цифрового преобразователя, выход которого подключен к цифровому сигнальному процессору, цифровой сигнальный процессор связан с запоминающим устройством и приемо-передатчиком, выходы которого являются выходами устройства, а также со входом первого цифроаналогового преобразователя, выход которого подключен ко входам задания порога ...

ПРИЗМАТИЧЕСКИЙ ДЕТЕКТОР

Призматический детектор ионизирующего излучения, содержащий сцинтиллирующие элементы, выполненные в виде стержней, и фотодиоды, обеспеченные выводами для соединения со схемами регистрации сцинтилляционных вспышек, отличающийся тем, что сцинтиллирующие элементы выполнены в виде стержней с сечением в виде равностороннего треугольника, фотодиоды расположены на треугольных торцах стержней, стержни установлены в ряд параллельно и вплотную друг к другу, между их вершинами расположен такой же ряд стержней треугольного сечения, а параллельно с зеркальным отображением расположены еще два ряда стержней, плоскости смежного дополнительного ряда расположены на плоскостях стержней предыдущего ряда.

ИЗБИРАТЕЛЬНЫЙ ДЕТЕКТОР ДЛЯ РЕГИСТРАЦИИ ИМПУЛЬСНОГО НЕЙТРОННОГО ИЗЛУЧЕНИЯ В СМЕШАННЫХ ГАММА-НЕЙТРОННЫХ ПОЛЯХ

Изобретение относится к регистрации импульсного нейтронного излучения в смешанных гамма-нейтронных полях и может найти применение в импульсных ядерных реакторах. Цель изобретения - повышение чувствительности и избирательности. Детектор содержит чувствительный элемент, регистрирующий нейтронное излучение, и конвертер нейтронного излучения, причем чувствительный элемент расположен внутри конвертера. Конвертер выполнен толщиной d>5l,где 1 - длина свободного пробега гамма-излучения, из материала с атомным номером Z≥ 50, с коэффициентом ослабления гамма-излучения μ>0,6см-1, с сечением взаимодействия нейтронов с гамма-излучением sn≥1,5•10-2см-1 . В корвертере происходит реакция радиационного захвата. В результате чувствительный элемент регистрирует прямое нейтронное излучение, и возникшее в конвертере гамма-излучение. К тому же конвертер является защитой чувствительного элемента от сопутствующего нейтронному гамма-излучения, В качестве чувствительного элемента можно использовать полупроводник ...

СПОСОБ ОПРЕДЕЛЕНИЯ ПЛОТНОСТИ ПОТОКА ТЕПЛОВЫХ НЕЙТРОНОВ В ПУЧКАХ НЕЙТРОННОГО ИЗЛУЧЕНИЯ И УСТРОЙСТВО ДЛЯ ЕГО ОСУЩЕСТВЛЕНИЯ

Использование: метрология нейтронного излучения и измерение тепловых нейтронов в реальных нейтронных полях. Сущность изобретения: основано на методе пропускания тепловых нейтронов заданного сечения, получаемого с помощью формирователя, образованного кадмиевым экраном и двумя коллимирующими окнами кадмиевого коллиматора-держателя со съемным He-3-поглотителем, размещенного на конце счетчика. 2 с. и 1 з.п. ф-лы, 1 ил.

СПОСОБ ИЗМЕРЕНИЯ ФИЗИЧЕСКИХ ВЕЛИЧИН НЕЙТРОННОГО ИЗЛУЧЕНИЯ F

Прибор для выделения нейтронов с заданной скоростью из их потока, например, для анализа веществ по спектру поглощения нейтронов

Способ оценки доз от быстрых нейтронов в массовом дозиметрическом контроле

Изобретение относится к экспериментальной ядерной физике и может быть использовано в индивидуальной дозиметрии. Цель изобретения - повышение достоверности оценки дозы от быстрых нейтронов за счет дискриминации потоков нейтронов на фоне высокоэнергетичного однозарядного излучения. Для этого обрабатывают экспонированную в радиационном поле ядерную пленкуj обрабатывают в амидоловом проявителе со следующего состава, г/л: сульфат натрия 3-4, роданистый натрий 0,8-1,5. бромистый калий 0,2-0.5; амидол 3-4. Изобретение позволяет оценить реальный вклад в дозу быстрых нейтронов.

Эмиссионный детектор для измерения нейтронов и гамма-излучения и способ его изготовления

... 1 . Эмиссионный детектор для, измерения нейтронов и гамма-излучения, состоящий из эмиттера, электрического изолятора и коллектора, о т л и ч а ющ и и с-я тем, что, с целью улучшения метрологических характеристик и повьшения надежности, эмиттер состоит из оболочки, выполненной из материала коллектора, и порошкообразного материала, например, изGdgOa или , ЗшгОз, , , , NdjO,, ХГзОз, , LiiO«i, HfO-j, СозОц., CdO, U30g,Th02, Co или их-смеси, 2.Способ изготовления детектора по п. 1, состоящий в том, что к детектору подсоериняют кабель для передачи сигналов путем соединения эмиттера с центральной жилой кабеля, а коллектора - с оболочкой кабеля, отличающийся тем, что, берут тру (Л бу-заготовку эмиттера, засыпают в нее лорошкообразный материал эмиттера , герметизируют по концам, устанавливают коаксиально в трубу-заготовку коллектора, изолируют их электроизоляциниьн материалом, производят протяжку заготовки детектора до требуемого диаметра, отжигают для снятия наклепа и разрезают полученный кабель ...

Способ определения кратностей нейтронной компоненты космических лучей

Установка для измерения электрического дипольного момента нейтрона

УСТАНОВКА. ДЛЯ ИЗМЕРЕНИЯ ЭЛЕКТРИЧЕСКОГО ДИГОЛЬНОГО МОМЕНТАНЕЙТРОНА, вюдачакнцая высоковольтную 'накопительную камеру ультрахолодных нейтронов с источником знакопеременного напряжения и стабилизатор магнитного поля с магниточувстви- тельшФШ элементами модуля вектора магнитного поля и источником питания, отличающаяся тем, что, с целью повышения точности измеренияj каждый магниточувст- вительный элемент стабилизатора снабжен компенсационной катушкой, подключенной к источнику .питания.АО(Л ...

Способ определения дозы нейтронов

Изобретение относится к способу определения дозы нейтронов с помощью ядерных фотоэмульсий и может быть использовано для индивидуального дозиметрического контроля. Целью изобретения является повышение достоверности определения дозного поля. Цель достигается тем, что экспонированную в исследуемом дозном поле фотопленку обрабатывают по режиму двухтемпера- ту рного проявления в амидоловом проявителе , содержащем дополнительно лимонную кислоту и бромистый калий в количествах 2 и 5 г/л соответственно . Действие лимонной кислоты .согласно данному предложению основано на уменьшении активной части проявляющего вещества, ; что сказывается на некотором снижении скорости процесса проявления в целом. Эффект от введения бромистого калия сводится к торможению скорости индукционного периода проявления, в первую очередь скрытого изображения, -образованного слабоионизирующим излучением. Совместное действие лимонной кислоты и КВг обеспечивает дискриминацию различных видов излучения, что позволяет избавиться ...

Способ измерения спектра нейтронов импульсного источника

Способ регулирования чувствительности устройства для регистрации быстрых нейтронов

СПОСОБ РЕГУЛИРОВАНИЯ ЧУВСТВИТЕЛЬНОСТИ УСТРОЙСТВА ДЛЯ РЕГИСТРАЦИИ БЫСТРЫХ НЕЙТРОНОВ с плоским полупроводниковым детектором,с интегральным дискриминатором, с помощью водородсодержащёго радиатора протонов отдачи, помещенного перед чувствительной областью полупроводникового детектора , отличающийся тем, что, с целью обеспечения регулируемой чувствительности в области 1энергии нейтронов ,5- 100 МэВ в мононаправленном и изотропном полях нейтронов, уменьшения фона от сопутствующего гамма-излучения и от реакций нейтронов с веществом детектора, упрощения процесса регулирования, толщину чувствительной области W полупроводникового Детектора задают такой , чтобы выполнялись соотношения В.В/ §-(Е,) Е, где В - порог дискриминатора; средняя на пути, равном W, удельная потеря энергии в веществе детектора протона с начальной энергией, равной Е, R(B) - пробег в детекторе прото (Л на с начальной энергией, равной В, а t тт толщину водородсодержащего радиатора задают постоянной для каждого устройства в пределах ...

Способ определения скорости образования дефектов в полупроводниковых материалах под действием нейтронного излучения

Способ получения атомной энергии

Термонейтронный датчик

DETECTOR OF CURRENT DENSITY OF DIRECTED NEUTRON RADIATION

APPARATUS FOR RECORDING FIUENT OF NEUTRONS

Датчик промежуточных и быстрых нейтронов

Дозиметр быстрых нейтронов

Применение магнитодиода в ка- ...

Устройство для регистрации направленных потоков ядерных излучений

Детектор с водородсодержащим диэлектриком

Изобретение относится к технике регистрации нейтронов и может быть использовано при определении плотности и флюенса импульсных потоков нейтронов на ядерных реакторах. Цель изобретения - увеличение точности регистрации быстрых нейтронов путем снижения регистрации быстрых нейтронов путем снижения относительного вклада сигнала соответствующего гамма-излучения и исключения- зависимости показаний от направленного распространения нейтронов. Детектор с водородсодержащим диэлектриком (ДВЛ) содержит заключенные в металлическом корпусе сигнальный электрод, сопряженный с противоположных сторон с водородсо- держащими диэлектриками и установленные со стороны корпуса с противопо- . ложных сторон вплотную к водпродсо- держащим диэлектрикам два охранных электрода, выполненных толщиной более средней длины пробегов прогоног отдачи и отделенные от корпуса слоями водородеодержащего диэлектрика.Скг- нальный электрод и слой аодородсо- держащего диэлек -.-рика между охрайны- ми элeктpoдa и и корпусом вьпюлпань ...

Аксиальный накопитель нейтронов

Дифференциальный спектрометр ультрахолодных нейтронов

Устройство для определения поляризационных характеристик ферромагнитных пленок на ультрахолодных нейтронах

Изобретение относится к приборам для определения поляризационных характеристик ферромагнитных пленок на ультр4холодных нейтронах. Целью изобретения является повышение точности определения поляризационных характеристик и упрощение устройства. Это достигается тем, что устройство содержит нейтроновод в разрыве которого установлена пленка, соединенная с ловушкой двумя отрезками U-образ- ной формы, а внутрь ловушки введен отражатель нейтронов с возможностью перемещения вдоль ловушки. 1 ил. сл со О) 09 ...

Устройство для регистрации флюенса нейтронов

Камера деления для измерения нейтронов

Способ регистрации нейтронов

DETECTOR OF NEUTRON RADIATION

Способ измерения нейтронных сечений

Устройство для обнаружения и локализации частиц потока нейтральных частиц

Использование: обнаружение и локализация частиц потока нейтральных частиц. Сущность изобретения; детектор содержит плоский твердый преобразователь, размещенный в касательном падении, сеть проводов усиления зарядов с использованием стимулированной ионизации газа и дорожка накопления зарядов. Эти дорожки размещаются в непосредственной близости к преобразователю и имеют с ним один и тот же электрический потенциал. Применяется при формировании изображений. 5 з.п. ф- лы. 6 ил.

Neutron flux distribution measured using activated probes - of pure vanadium esp in twisted wire form

A device for measuring the neutron flux distribution in the fission zone of a reactor comprises probes which are carried by a gas through pipes into and out of the core; their activity is measured by stationary activity meters after they emerge from the core. The probes are of pure vanadium and their beta-activity is measured by the activity meter. Probes are pref. of cord layed up from vanadium wire without hemp core, their ends being welded. The activity metering elements are pref. semiconductor diodes, and the measurements are pref. carried out as the probe moves past a single element. The use of pure vanadium avoids the prodn. of a large range of nuclides which lead to false readings. The twisted cords are sufficiently robust to withstand impact. They are flexible and easier to handle than the conventional column of balls, used as detector elements.

SELBST STROM LIEFERNDE STRAHLUNGSDETEKTOREN

STRAHLUNGSFLUSS-MESSANORDNUNG

SICH SELBST MIT ENERGIE VERSORGENDER GAMMASTRAHLUNGSDETEKTOR

GERAET UND VERFAHREN ZUR UEBERWACHUNG DES AUSGANGS EINES NEUTRONENDETEKTORS

Vorrichtung zur Erweiterung des Messbereichs von Detektoren für Neutronen mit Energien kleiner gleich 10 MeV

Vorrichtung zur Erweiterung des Messbereichs eines Detektors für Neutronen mit Energien ≤ 10 MeV, mindestens aufweisend eine Hülle, die mindestens den Körper des Detektors im Bereich eines Nachweiswinkels eines Nachweisgerätes des Detektors umhüllt, wobei – die Hülle und eine Oberfläche des Detektors einen Abstand aufweisen, der gering genug ist das Nachweisgerät des Detektors vermittels der Hülle vor einem Einfall von Streustrahlung abzuschirmen, – die Hülle aus einem Material gebildet ist, das einen Wirkungsquerschnitt bei Neutronenenergien von 100 MeV von σ ≥ 1,8 Barn aufweist, – ein Produkt aus dem Wirkungsquerschnitt σ und einer Teilchendichte n des Materials der Hülle und einer Wandstärke x der Hülle σMaterial·nMaterial·xWandstärke ≥ 0,06 ist und – die Wandstärke x der Hülle gering genug ist eine Selbstabsorption von Neutronen in der Hülle auszuschließen.

Vorrichtung zur Bestimmung der thermischen Neutronenflußmultiplikation und der Neutronenemission

METHODS AND APPARATUS FOR TESTING THE INDIVIDUAL ACTIVITIES OF PROBE BODIES THAT HAVE BEEN IRRADIATED, FOR EXAMPLE IN A NUCLEAR REACTOR INSTALLATION

... 1,209,826. Reactors. SIEMENS A.G. 11 March, 1968 [11 March, 1967], No. 11833/68. Heading G6C. [Also in Divisions G1 and H5] The activities of probe bodies which have been irradiated, e.g. in a nuclear reactor, are measured or tested by arranging them in a file in a conveyer tube 2 adjacent to which an activity evaluating device 1 is disposed and moving the bodies in turn past the device by the controlled movement along the inside of the tube of a wire 4, one end of which acts against the end of the file. Preferably the probe bodies are spherical and are moved through the radioactive environment and into the conveyer tube 2 by means of compressed gas. As shown in the Figure, the probe bodies 3 may be stacked in a column resting on one end of the wire which is preferably moved downwards. The wire 4 may be resilient, and movement of the wire may be induced by its being wound round and secured to a drum 40 at the end of the conveyer tube, the drum being rotatable about axis 42 to initiate movement ...

Improvements in and relating to signal handling and processing

Self-powered radiation detectors

A self-powered nuclear radiation detector with an emitter electrode of an alloy of a first major constituent metal having a desired high radiation response, and a second minor constituent which imparts to the alloy a desired thermal or mechanical characteristic without diminishing the desired high radiation response. A gamma responsive self-powered detector is detailed which has an emitter with lead as the major constituent, with the minor constitutent selected from aluminum, copper, nickel, platinum, or zinc.

Temperature, Pressure and Neutron Fluence Measurment

A sensor is provided for combined measurement of temperature and neutron fluence. The sensor uses first optical body having at opposing, spaced sides an incident surface and a reflecting surface. It also has a second optical body with a higher finesse mirrored surface. The sensor further comprises an optical pathway for carrying incident light to the incident surface. The first optical body, nearest the pathway, acts as a Fabry Perot etalon and the second, including the cavity between the first and second, as a Fabry-Perot interferometer. Varying the temperature of the first optical body leads to changes in the spacing between the incident and reflecting surfaces of the first optical body. Varying the pressure deforms the second optical body. Each is made of a material, e.g. sapphire, whose optical absorbance increases depending on the neutron fluence. A characteristic attenuation is produced in the reflected light.

Improved radiation dosimeter system

... 1,022,788. Dosimeter systems. UNITED STATES ATOMIC ENERGY COMMISSION. Sept. 3, 1963 [Sept. 11, 1962], No. 34657/63. Heading G1A. A dosimeter system for determining the neutron dose received by a human-being from a radiation incident is constructed so as to be portable, to take into account the time between the incident and the test, and to be capable of rapid and simple operation. The system includes a portable battery-powered detector unit consisting of a probe coupled by flexible leads to power supply and indicator assembly. The probe includes a sodiumiodide scintillator crystal associated with a photomultiplier and wrapped in insulating tape and a lead sheath. The complete probe is aluminium cased. The photo-multiplier output is fed back to amplifier stages and an indicating meter. The meter circuitry includes switched potentiometers allowed for correction of the meter reading in view of the time that has elapsed between the incident and the test, a further switch changing the value ...

Discriminating pulse types

A method and apparatus for discriminating between different types of pulses (2, 4) output by a radiation detection system; comprising performing the discriminating based on the different respective shapes of the different types of pulses(2, 4). The discriminating may comprise: receiving (s2; s22) the output pulses (2, 4); generating (s12, s14; s32, s34) respective template pulses for the types of pulses to be discriminated; and determining (s16, s36) correlations (125, 136) between the shapes of the received pulses and the template pulses; differing levels of correlation determined for the respective different types of pulses providing the discrimination between the types of pulses. The discriminating may further comprise detecting (s6; s26) the presence of the received output pulses (2, 4) and performing normalising.

Apparatus and methods for monitoring output from pulsed neutron sources

AUTOMATIC CONTROL OF MOVABLE DETECTORS

METHOD FOR PREPARING NEUTRON-ACTIVATION DETECTORS

... 1349113 Detecting neutrons INSTITUT PHIZIKI AKADEMII NAUK GRUZINSKOI SSR 28 Feb 1972 9076/72 Heading G6P In a neutron detector, the detector material, which may be sulphur, phosphorus or a nitrate of cobalt, nickel, zinc, gold, indium or iron, is added as a powder to a liquid polycondensation resin. In an alternative form the detecting metal may be in the form of acetates. In this case, alcoholic solutions are formed of the salts and the resin which are then mixed and distilled. A powdered graphite filler may be added to the resin and the mixture is hardened by heating and then ground to a powder after cooling.

SENSORS FOR USE NUCLEAR REACTOR CORES

ELECTRICAL CONDUCTORS

... 1487271 Coaxial cable BABCOCK & WILCOCK CO 28 Jan 1975 [5 April 1974] 3683/75 Heading H1A A coaxial cable is constructed using conductive sheath and lead-wire materials that have a low probability for neutron-electron reactions, the lead-wire material having an atomic number greater than the sheath material and the sizes of the lead-wire and sheath being so interelated that electron emission by them in response to photoelectric and Compton phenomena are substantially equal. An equation is given in the Specification from which are derived typical values of an Inconel (R.T.M.) sheath of 0À053 inch o.d. and 0À007 inch thick with a Zircalloy lead-wire 0À0075 inch diameter. The lead-wire diameter may be increased to compensate for thermionic and neutron-electron emissions, and an insulator of low neutron absorption may be interspaced between lead-wire and sheath. The cable is useful as a detector cable in a nuclear reactor.

An improved method and device for measuring doses of thermal neutrons

... 866,112. Actuation of switches. COMMISSARIAT A L'ENERGIE ATOMIQUE. Nov. 4, 1958 [Nov. 8, 1957], No. 35337/58. Class 38 (5). [Also in Group XL (a)] A switch responsive to a given integrated neutron, flux (dose) comprises a sensitive element 1 which flexes upwards in proportion to the dose received, and a pair of electrical contacts 13 which are closed when the element 1 flexes by a given amount. Closing of the contacts 13 may operate an indicator and at the same time energize a heating element to heat the container 12 enclosing the switch, heat having the effect of annealing the sensitive element 1 and restoring it to its initial position. The element 1 may be a plate of glass containing 60% boron trioxide and may be shielded from neutron bombardment from below by a neutron absorbing screen, for example of cadmium.

Portable time-of-flight fast neutron spectroscopy

A time of flight neutron spectroscopy system 100 comprising a first detector 120 positioned at a first distance 130 from a fission source 110, configured to detect a gamma-ray emitted from the fission source 110 and a second detector 140 positioned at a second distance 150 from the fission source 110, configured to detect a neutron emitted from the fission source 110. A computer system 160 which may include a mixed field analyser (MFA) to discriminate gamma and neutron interactions records the time of a gamma ray detection at the first detector to start a time window. Detection of a neutron at the second detector 140 within the time window, record the gamma and neutron detections as a coincidence event. The time difference between the detections determines time-of-flight and neutron energy. The first detector may be solid-state scintillator and the second a liquid scintillator. The system may be portable or for on-the-fly spectroscopy.

DETECTOR FOR IONIZING RADIATION AND PROCEDURE FOR THE PRODUCTION OF THE SAME

NEUTRONENDETEKTOR

PROCEDURE AND DEVICE FOR THE MEASUREMENT OF A COUNTING RATE

NEUTRON DETECTOR

COAXIAL CABLE CONNECTION TO NEUTRON DETECTORS

PROCEDURE AND USE OF A DEVICE FOR THE FORECAST OF VOLCANIC OUTBREAKS AND EARTHQUAKES

ARRANGEMENT FOR COLLECTION THAT INTEGRALS LOCAL DOSE OF SURROUNDINGS OF RADIATION HIGH-ENERGY.

COAXIAL CABLE CONNECTION TO NEUTRON DETECTORS

PROCEDURE FOR THE DETERMINATION OF NEUTRON SPECTRA, AND DEVICE FOR THE EXECUTION OF THE PROCEDURE

Neutron and gamma ray monitor

An apparatus for selective radiation detection includes a neutron detector that facilitates detection of neutron emitters, e.g. plutonium, and the like; a gamma ray detector that facilitates detection of gamma ray sources, e.g., uranium, and the like. The apparatus comprises a first light guide, optically coupled to a first optical detector; a second light guide, optically coupled to a second optical detector a sheet of neutron scintillator, opaque for incoming optical photons, said sheet of neutron scintillator sandwiched between the first and the second light guides. The second light guide comprises a gamma ray scintillator material.

Slow neutron conversion body and slow neutron detector

The present application, pertaining to the field of slow neutron detection, relates to a slow neutron converter and a slow neutron detector. The slow neutron converter includes a substrate, the substrate including a plurality of holes extending along a first direction and insulating walls between the plurality of holes, wherein the plurality of holes are through holes. The slow neutron converter further includes a boron layer at least covering an exposed surface of the plurality of holes. The slow neutron converter and the slow neutron detector having the slow neutron converter according to the present disclosure are capable of maintaining a high slow neutron detection efficiency. In addition, the manufacturing complexity and manufacturing cost of the detector are reduced, and thus the effective, convenient and low-cost slow neutron detection is achieved. (Fig. 2) chbm A0137553776v1 120640689 ...

Nuclear reaction protection system

Nuclear reaction protection system

Improvements in and relating to signal handling and processing

SELF-POWERED NEUTRON DETECTOR

RADIOGRAPHIC EQUIPMENT

The invention concerns radiographic equipment. The equipment includes a source of substantially mono-energetic fast neutrons produced via the deuterium- tritium or deuterium-deuterium fusion reactions, comprising a sealed-tube or similar generator for producing the neutrons. The equipment further includes a source of X-rays or gamma-rays of sufficient energy to substantially penetrate an object to be imaged and a collimating block surrounding the neutron and gamma-ray sources, apart from the provision of one or more slots emitting substantially fan-shaped radiation beams. Further included is a detector array comprising a multiplicity of individual scintillator pixels to receive radiation energy from the sources and convert the received energy into light pulses, the detector array aligned with the fan-shaped beams emitted from the source collimator and collimated to substantially prevent radiation other than that directly transmitted from the sources reaching the array. Conversion means ...

DETECTION OF NUCLEAR RADIATION

A method of detecting, counting or otherwise measuring nuclear radiation includes the steps of exposing a diamond containing single substitutional paramagnetic nitrogen to the nuclear radiation to cause electrons or holes to be trapped at lattice imperfections within the diamond crystal structure, heating the diamond to cause it to luminesce and utilising the luminescence as a means for the detection, counting or measurement of the nuclear radiation. The method is characterised by subjecting the diamond to a high dose of neutron or electron irradiation prior to exposing it to the nuclear radiation to be detected. This, it has been found, improves both the sensitivity of the diamond as a thermoluminescent material and linearity of the thermoluminescent response to nuclear radiation dose.

SELF-POWERED RADIATION DETECTOR WITH STRANDED WIRE EMITTER

... 7 45,874 An improved flexible self-powered radiation detector wherein the elongated central conductive emitter is formed of a plurality of small diameter stranded wires of the desired emitter material to improve the flexibility of the detector. Insulating means is provided about the stranded emitter, and a thin conductive sheath is provided about the insulating means.

COMPOSITE PROMPT/DELAYED INCORE DETECTOR ASSEMBLY

MINERAL INSULATED COAXIAL CABLE FOR NEUTRON DETECTORS

HIGH RESOLUTION MULTIPLEXING SYSTEM

A method is provided for measuring time varying particle fluxes with improved temporal resolution and signal to noise ratio. The particles can be photons, neutrons, electrons or electrically charged particles. The method includes a set of electronic and/or optical components and a set of algorithms that implement N-fold temporal multiplexing of the input flux. The system can be used to measure other types of flux by using a transducer to convert the flux into a compatible form. The system can include a transducer such as a scintillator that operates to convert particle flux incident into a photon flux proportional to the amplitude of particle flux. The invention can be used with multiplexing methods known to those skilled in the art, for example Hadamard and Fourier methods.

COVERT SURVEILLANCE USING MULTI-MODALITY SENSING

The present specification discloses a covert mobile inspection vehicle with a backscatter X-ray scanning system that has an X-ray source and detectors for obtaining a radiographic image of an object outside the vehicle. The system is configured to also simultaneously detect passive radiation. The systems preferably include at least one sensor for determining a distance from at least one of the detectors to points on the surface of the object being scanned, a processor for processing the obtained radiographic image by using the determined distance of the object to obtain an atomic number of each material contained in the object, and one or more sensors to obtain surveillance data from a predefined area surrounding the vehicle.

Позиционно-чувствительный детектор

Позиционно-чувствительный детектор, содержащий три вложенных друг в друга цилиндрических набора сцинтиллирующих элементов с общей осью параллельной оси детектора, сцинтиллирующие элементы внешнего и среднего набора выполнены из материала для регистрации тепловых нейтронов и разделены цилиндрическим экраном, поглощающим тепловые нейтроны, сцинтиллирующие элементы внешнего, среднего и центрального наборов снабжены светоотражающими оболочками, на светоотражающие оболочки сцинтиллирующих элементов нанесено светонепроницаемое покрытие, противоположные торцы каждого сцинтиллирующего элемента внешнего, среднего и центрального наборов соединены посредством оптических соединителей с двумя волоконными световодами, находящимися с противоположной стороны в оптическом контакте с двумя матричными фотоприемниками, число фоточувствительных элементов в каждом матричном фотоприемнике равно или больше числа сцинтиллирующих элементов, отличающийся тем, что сцинтиллирующие элементы центрального набора выполнены из водородосодержащего сцинтиллятора, применяемого для регистрации быстрых нейтронов, а цилиндрический экран, поглощающий тепловые нейтроны, установлен на поверхность сцинтиллирующих элементов среднего набора. РОССИЙСКАЯ ФЕДЕРАЦИЯ (19) RU (11) (51) МПК G01T 3/00 (13) 166 127 U1 (2006.01) ФЕДЕРАЛЬНАЯ СЛУЖБА ПО ИНТЕЛЛЕКТУАЛЬНОЙ СОБСТВЕННОСТИ (12) ТИТУЛЬНЫЙ (21)(22) Заявка: ЛИСТ ОПИСАНИЯ ПОЛЕЗНОЙ МОДЕЛИ К ПАТЕНТУ 2016125268/28, 24.06.2016 (24) Дата начала отсчета срока действия патента: 24.06.2016 (72) Автор(ы): Микеров Виталий Иванович (RU) Приоритет(ы): (22) Дата подачи заявки: 24.06.2016 (45) Опубликовано: 20.11.2016 Бюл. № 32 1 6 6 1 2 7 R U (57) Формула полезной модели Позиционно-чувствительный детектор, содержащий три вложенных друг в друга цилиндрических набора сцинтиллирующих элементов с общей осью параллельной оси детектора, сцинтиллирующие элементы внешнего и среднего набора выполнены из материала для регистрации тепловых нейтронов и разделены цилиндрическим экраном, ...

Absolute nuclear material assay using count distribution (lambda) space

A method of absolute nuclear material assay of an unknown source comprising counting neutrons from the unknown source and providing an absolute nuclear material assay utilizing a model to optimally compare to the measured count distributions. In one embodiment, the step of providing an absolute nuclear material assay comprises utilizing a random sampling of analytically computed fission chain distributions to generate a continuous time-evolving sequence of event-counts by spreading the fission chain distribution in time.

Neutron detection by neutron capture-initiated relaxation of a ferroelectrically, ferromagnetically, and/or chemically metastable material

A system for detecting radiation using an array of cells containing a metastable material together with sensing apparatus and display apparatus.

System and Method For Measuring and Analyzing Target Emissions

An interrogation component is controllable between three detection/timing modes: neutron generator OFF for predetermined amount of time (Mode 1), neutron generator pulsing at 5-10 kHz/2-10 microseconds (Mode 2), and neutron generator pulsing at 200-400 Hz/25-200 microseconds (Mode 3). Utilizing the interrogation component in the three detection/timing modes to inspect a target facilitates data collection in both passive and active modes for both passive and stimulated emissions of gamma and neutron radiation.

Boron-10 compounds for neutron capture layer

A neutron detector includes a shell bounding an interior volume. A portion of the neutron detector serves as a cathode. The detector includes a central structure located within the interior volume and serving as an anode. The detector includes a boron coating on the interior of the wall wherein at least some of the boron coating is heat diffused into the wall from a boron-containing powder to form the boron coating which is sensitive to neutrons. The detector includes an electrical connector operatively connected to the central structure for transmission of a signal collected by the central structure. An associated method of heat diffusing the boron includes subjecting boron-containing powder to an elevated temperature so that a quantity of the boron-containing powder heat diffuses.

DETECTOR AND METHOD FOR DETECTING NEUTRONS

A neutron detector includes a bulk of a neutron moderating material, a first housing consisting of or comprising a gamma ray attenuating material, a second housing consisting of or comprising a gamma ray attenuating material, a first sensor device comprising a gadolinium cover disposed in the first housing, and a second sensor device disposed in the second housing. The first sensor device and the second sensor device are each sensitive to gamma rays. The first housing and the second housing are arranged adjacent to each other in the bulk. 111-. (canceled)12. A neutron detector comprising:a bulk of a neutron moderating material;a first housing consisting of or comprising a gamma ray attenuating material;a second housing consisting of or comprising a gamma ray attenuating material;a first sensor device comprising a gadolinium cover disposed in the first housing; anda second sensor device disposed in the second housing,wherein,the first sensor device and the second sensor device are each sensitive to gamma rays, andthe first housing and the second housing are arranged adjacent to each other in the bulk.13. The neutron detector as recited in claim 12 , wherein the gamma ray attenuating material is lead.14. The neutron detector as recited in claim 12 , wherein the first housing and the second housing are arranged in a middle of the bulk.15. The neutron detector as recited in claim 12 , wherein the first sensor device and the second sensor device each have a same sensitivity to gamma rays.16. The neutron detector as recited in claim 15 , wherein the first sensor device and the second sensor device are empirically selected from a certain amount of sensor devices.17. The neutron detector as recited in claim 12 , wherein the first sensor device and the second sensor device each comprise at least one of a carbon-doped alumina such as α-AlO:C claim 12 , a titan and magnesium-doped lithium fluorid (LiF:Ti claim 12 , Mg) claim 12 , and a dysprosium-doped calcium fluoride (CaF:Dy ...

Neutron detector and method for detecting neutrons

A 10 B neutron detector and an associated method of detecting neutrons. The detector includes an exterior shell bounding and sealing an interior volume, a neutron-sensitive boron coating located on at least part of the exterior shell at the interior volume. One of the boron coating and the exterior shell serves as a cathode, and a central structure located within the interior volume and serves as an anode. The detector includes gas within the interior volume that conducts an electrical energy pulse between the cathode and the anode in response to a neutron impinging upon the neutron-sensitive boron coating. The gas includes a quantity of 3 He gas sensitive to neutron impingement and generating an electrical energy pulse for reception by the anode in response to a neutron impinging upon the 3 He gas. The method includes detecting at least one neutron via impingement of the neutron upon the 3 He gas.

CELLULAR THERMAL NEUTRON DETECTOR

The present invention provides a cellular thermal neutron detector, comprising: a cellular structure comprised of one or more hollow regular hexagonal prism-shaped cellular units, wherein a neutron absorbing material is coated on an inner side of a pipe wall of each of the cellular units. Since the neutron-sensitive cellular structure is employed, the present invention can perform thermal neutron detection without using the scarce nuclide 3He, and effectively reduce the manufacture costs of the thermal neutron detector. Further, the present invention has characteristics such as a reduced or eliminated neutron detecting dead zone. 1. A thermal neutron detector comprising:a cellular structure comprised of one or more hollow regular hexagonal prism-shaped cellular units, wherein a neutron absorbing material is coated on an inner side of a pipe wall of each of the cellular units.2. The thermal neutron detector according to claim 1 , whereinthe pipe wall of each of the cellular units is electrically grounded;an anode wire is provided along a central axis of each of the cellular units; anda chamber of each of the cellular units is filled with a proportional working gas.3. The thermal neutron detector according to claim 2 , further comprising:a supporting frame surrounding a radial outer side of the cellular structure; anda first template and a second template respectively having a central opening and being fixed on the supporting frame in a way of adjoining or being adjacent to either end of the cellular structure.4. The thermal neutron detector according to claim 3 , whereinthe cellular structure is connected to the supporting frame via a plurality of groups of springs evenly distributed along an envelope circumferential line of the cellular structure, to maintain spatial stability of the cellular structure, wherein each group of springs are comprised of at least two springs spaced apart from each other along a longitudinal axis of the supporting frame.5. The thermal ...

STRESS REDUCTION FOR PILLAR FILLED STRUCTURES

According to one embodiment, an apparatus for detecting neutrons includes an array of pillars, wherein each of the pillars comprises a rounded cross sectional shape where the cross section is taken perpendicular to a longitudinal axis of the respective pillar, a cavity region between each of the pillars, and a neutron sensitive material located in each cavity region. 1. An apparatus for detecting neutrons , comprising:an array of pillars, wherein each of the pillars comprises a rounded cross sectional shape where the cross section is taken perpendicular to a longitudinal axis of the respective pillar;a cavity region between each of the pillars; anda neutron sensitive material located in each cavity region.2. The apparatus of claim 1 , wherein the neutron sensitive material is Boron-10 (B).3. The apparatus of claim 1 , wherein each of the pillars comprises an aspect ratio of less than about 50:1.4. The apparatus of claim 1 , wherein each of the pillars comprises silicon (Si).5. The apparatus of claim 1 , wherein the rounded cross sectional shape of each of the pillars is at least one of circular and ellipsoid.6. The apparatus of claim 1 , wherein the neutron sensitive material does not completely fill the cavity region claim 1 , thereby defining gaps in the cavity region that are not filled with the neutron sensitive material.7. The apparatus of claim 6 , wherein the gaps are filled with a second material.8. The apparatus of claim 1 , wherein the array is segmented into discrete segments of the pillars claim 1 , wherein an average distance between adjacent pillars in each of the segments is less than an average distance between adjacent segments.9. The apparatus of claim 1 , wherein a spacing is present between the pillars and the neutron sensitive material.10. A method for forming the apparatus of claim 9 , the method comprising:forming the pillars;applying a sacrificial layer to the pillars;depositing the neutron sensitive material in the cavity region over the ...

NON-INTRUSIVE METHOD TO IDENTIFY PRESENCE OF NUCLEAR MATERIALS USING ENERGETIC PROMPT NEUTRONS FROM NEUTRON-INDUCED FISSION

Methods and systems for non-intrusively detecting the existence of fissile materials in a container via the measurement of energetic prompt neutrons are disclosed. The methods and systems use the unique nature of the prompt neutron energy spectrum from neutron-induced fission arising from the emission of neutrons from almost fully accelerated fragments to unambiguously identify fissile material. These signals from neutron-induced fission are unique and allow the detection of any material in the actinide region of the nuclear periodic table. 1. (canceled)2. (canceled)3. (canceled)4. (canceled)5. (canceled)6. A method of detecting a presence of a material comprising an actinide in a container , comprising:a) locating at least one neutron detector such that said detector views said container at a first angle relative to a first incident neutron beam;b) illuminating at least a portion of said container with said first incident neutron beam, wherein said first incident neutron beam comprises neutrons with a first predetermined incident neutron energy>1 MeV.;c) detecting, in at least one said neutron detector viewing said container at the first angle, a plurality of prompt neutrons produced by a fission interaction of said first incident neutron beam with at least a portion of said container;d) for at least one of said detected prompt neutrons, determining a minimum energy of said detected prompt neutron; ande) based upon the determined minimum energy of a predetermined quantity of said detected prompt neutrons exceeding a predetermined value, determining that the material comprising the actinide is present in the container.7. The method of claim 6 , wherein determining the minimum energy of said detected neutron comprises measuring a time of flight of said detected neutron.8. The method of claim 6 , wherein determining the minimum energy of said detected neutron comprises analyzing a quantity of energy deposited in at least one of said neutron detectors.9. The method of ...

NEUTRON MEASUREMENT APPARATUS AND NEUTRON MEASUREMENT METHOD

A neutron measurement apparatus includes: an analog signal processor; a digitizing processor; an FFT calculation processor; and a signal processor. The analog signal processor amplifies alternating current components of detector output signals output from a neutron detector, and filters to remove high frequency components from the output signals, which the digitizing processor digitizes at a constant sampling period in a time series; the FFT calculation processor converts certain of the signals in a time domain from the digitizing processor into signals in a frequency domain, and filters the signals in the frequency domain; and the signal processor selects and extracts signals having required frequency components through the calculation processing on the FFT calculation processor, to calculate power spectral densities of the extracted signals, and to convert the calculated power spectral densities into a neutron measurement value. 1. A neutron measurement apparatus comprising:an analogue signal processing system configured to amplify alternating current components of detector output signals output from a neutron detector, and to apply filtering to remove high frequency components from the output signals;a digitizing processing system configured to digitize the output signals output from the analogue signal processing system at a constant sampling period in a time series;a FFT calculation processing system configured to convert a certain number of the signals in a time domain output from the digitizing processing system into signals in a frequency domain, and to apply filtering to the signals in the frequency domain; anda signal processing system configured to select and extract signals having required frequency components through the calculation processing on the FFT calculation processing system, so as to calculate power spectral densities of the extracted signals, and to convert the calculated power spectral densities into a neutron measurement value.2. The ...

TRAVELING REACTOR POWER MONITORING SYSTEM AND METHOD FOR MONITORING DRIVING TORQUE

A traveling reactor power monitoring system includes a drive control unit configured to drive a motor and move a traveling probe in a guide tube by driving the motor, a torque sensor configured to measure a drive torque of the motor, and a drive torque monitoring unit that generates an alarm when the measured drive torque exceeds a predefined upper threshold, and that bypasses generating the alarm for a predefined bypass time, the predefined bypass time starting at a time of starting driving the motor. 1. A traveling reactor power monitoring system for moving a traveling probe connected to a probe cable in a guide tube , comprising:a drive control unit configured to drive the motor and move the traveling probe in the guide tube by driving a motor;a torque sensor configured to measure a drive torque of the motor; anda drive torque monitoring unit that generates an alarm when the measured drive torque exceeds a predefined upper threshold, and bypasses generating the alarm for a predefined bypass time, the predefined bypass time starting at a time of starting driving the motor.2. The traveling reactor power monitoring system of claim 1 , wherein:the drive torque monitoring unit stops driving the motor when the drive torque exceeds the predefined upper threshold, and bypasses generating the alarm for the predefined bypass time when the drive control unit restarts driving the motor.3. The traveling reactor power monitoring system of claim 1 , wherein:the drive control unit drives the motor at a slower speed at a probe position that the drive torque is measured to exceed the upper threshold.4. The traveling reactor power monitoring system of claim 1 , wherein:the drive control unit stores a position of the probe when the measured drive torque of the motor is measured as exceeding the predefined upper threshold; andthe drive control unit moves the motor back and forth at the stored position of the probe that the measured drive torque exceeds the upper threshold.5. The ...

METHOD FOR DETECTING NUCLEAR MATERIAL BY MEANS OF NEUTRON INTERROGATION, AND RELATED DETECTION SYSTEM

A method for detecting nuclear material in an object analysed by neutron interrogation with an associated particle tube, where the method includes steps of detection of coinciding pulses by detector pixels of at least one matrix of detector pixels, where a step of detection of coinciding pulses leads to the formation of an event which reflects a fission reaction which occurs in the nuclear material, where the method includes a search for adjoining pixels amongst the pixels which have detected coinciding pulses, a grouping of adjoining pixels into groups of adjoining pixels, a count of the pixels and/or groups of adjoining pixels which have detected coinciding pulses, and a validation of the occurrence of an event provided at least three pixels and/or groups of adjoining pixels are counted. 2. A detection method according to claim 1 , in which the shot noise detected above the time threshold (T) is subtracted from the number of validated events which occur above the time threshold (T) claim 1 , such that the determination of the signal of the presence or absence of nuclear material in the object results from a comparison of the number of validated events counted in the counting step claim 1 , minus the shot noise with the alarm threshold.39. A detection method according to claim 1 , in which the step (E) of counting the validated events which occur above a time threshold (T) counted from the time reference (T) is a step of formation of a histogram.4. A detection method according to claim 1 , in which duration ΔT is predetermined in advance claim 1 , such that the counting of the number of validated events which occur above a time threshold claim 1 , the determination of the shot noise claim 1 , the calculation of the alarm threshold and the step of determination of the signal of the presence or absence of nuclear material are implemented once duration ΔT is completed.5. A detection method according to claim 1 , in which the counting of the number of validated events ...

CORE MONITORING SYSTEM

A core monitoring system including: a TIP measuring a neutron amount in a nuclear reactor; a TIP drive device; a TIP panel; a neutron monitoring panel; and a process computer. The TIP panel includes: a TIP level processor and a TIP position processor that process a TIP level signal and a TIP position signal input from the TIP drive device, respectively; a time setting section synchronizing the TIP level signal and the TIP position signal; and a TIP level data storage section storing synchronized TIP level data. The neutron monitoring panel includes a time setting section setting collecting time of a LPRM level signal and an APRM level signal. The process computer compares the time and stores the TIP level data from the TIP panel and the LPRM and APRM level signals from the neutron monitoring panel corresponding in time, and calculates core performance based on the TIP level data. 1. A core monitoring system comprising:a TIP (Traversing Incore Probe) that measures an amount of neutrons in a reactor core;a TIP drive device;a TIP panel;a neutron monitoring panel; anda process computer,the TIP panel including a TIP level processing section that processes a TIP level signal input from the TIP drive device, a TIP position processing section that processes a TIP position signal input from the TIP drive device, a TIP panel time setting section that sets a TIP panel time for synchronizing the TIP level signal and TIP position signal, and a TIP level data storage section that stores synchronized TIP level data,the neutron monitoring panel including a time setting section that sets a neutron monitoring panel time corresponding to a collection time of a LPRM (local power range monitoring) level signal and an APRM (average power range monitor) level signal,the process computer including a TIP level data database that compares a TIP time attached to the TIP level data transmitted from the TIP panel and a nuclear implementation console time attached to the LPRM level signal and ...

Multiplier Tube Neutron Detector

A neutron detecting device using a neutron-reactive material as the source of charged particles to feed conventional dynode-based electron multiplier which not gas-filled (i.e., with He). The detector comprises a neutron-reacting material that produces charged particles, coupled with an electron multiplier that is known for use in photomultipliers. The neutron-reacting material is deposited on a substrate at the entrance to the electron multiplier. Charged particles from the neutron-reacting material impinge on the first dynode of the electron multiplier, where, in turn, electrons are generated. The secondary electrons are collected by a second dynode, and the charge so collected is amplified in each succeeding dynode stage in a cascade effect. The charge pulse from the anode is processed by subsequent pulse processing electronics and counting electronics to provide a count rate that is proportional to the neutron flux incident on the neutron-reacting material. 1. A multiplier tube neutron detector , comprising:a vacuum tube and a substrate applied to a portion of the vacuum tube's internal surface;a neutron-reacting material deposited to the substrate that emits charged particles when impacted by a neutron;a first dynode on to which the charged particles are directed and where they generate secondary electrons; anda series of subsequent dynodes that multiply the number of electrons from a preceding dynode through the generation of secondary electrons;an anode that receives resulting secondary electrons current;wherein a current pulse is emitted at the anode at a rate proportional to neutron flux incident on the neutron-reacting material.2. The multiplier tube neutron detector according to claim 1 , further comprising an extraction grid positioned between the neutron-reacting material and the series of dynodes.3. The multiplier tube neutron detector according to claim 2 , wherein the extraction grid is biased positively with respect to the neutron-reacting material ...

Boron-Coated Straw Detectors With Shaped Straws

A system for detecting fissile materials which utilizes boron coated straw detectors in which the straws have non-circular cross sections. Embodiments include straws having star shaped cross sections of various configurations including a six pointed star. The system can include tubular housings having one or more shaped straws stacked within the housings. 1. An improved boron-coated straw detector system comprising a boron-coated straw having a non-circular cross section.2. The boron-coated straw detector system of claim 1 , wherein the straw's non-circular cross section comprises a star shape.3. The boron-coated straw detector system of claim 1 , wherein the non-circular straw is enclosed within a tubular housing.4. The boron-coated straw detector system of claim 2 , wherein the straw's star shaped cross section comprises a star shape having between 3 and 24 points.5. The boron-coated straw detector system of claim 2 , wherein the straw's star shaped cross section comprises a star shape having 6 points.6. The boron-coated straw detector system of claim 2 , wherein the outer portion of the star's point are rounded.7. The boron-coated straw detector system of claim 2 , wherein the star's valleys are rounded.8. The boron-coated straw detector system of claim 2 , wherein the star's valleys are rounded and the outer portion of the star's point are rounded claim 2 , and both the outer portion of the points and the valleys have about the same radius of curvature.9. The boron-coated straw detector system of claim 2 , wherein the outer portion of the star's points define a circle circumscribing the straw and wherein each of the star's valley's have approximately the same depth relative to the circumscribed circle.10. The boron-coated straw detector system of claim 2 , wherein the straw's star shaped cross section comprises a star shape having 6 points claim 2 , and wherein the star's valleys are rounded and the outer portion of the star's point are rounded claim 2 , and ...

BORON-COATED NEUTRON DETECTOR AND METHOD FOR MANUFACTURING THE SAME

A boron-coated neutron detector, comprising a cathode tube with a plurality of passages formed therein along its longitudinal direction, the inner wall of each passage being coated with boron material; an electrode wire serving as an anode and arranged longitudinally in each of the passages, the electrode wire adapted to be applied with high voltage; and an insulating end plate to which each end of the cathode tube is fixed, the electrode wire being fixed to the cathode tube via the insulating end plate. Preferably, the cathode tube is formed by jointing a plurality of boron-coated substrates. The boron-coated neutron detector increases the detection efficiency of the neutron detector, which may reach or even exceed the detection efficiency of the He neutron detector of the same size, and the cost thereof is much cheaper than the He neutron detector. 1. A boron-coated neutron detector , comprising:a cathode tube with a plurality of passages formed therein along its longitudinal direction, the inner wall of each passage being coated with boron material;an electrode wire serving as an anode and arranged longitudinally in each of the passages, the electrode wire adapted to be applied with high voltage; andan insulating end plate fixed to each end of the cathode tube, the electrode wire being fixed to the cathode tube via the insulating end plates.2. The boron-coated neutron detector according to claim 1 , wherein the cathode tube is formed by jointing a plurality of boron-coated substrates to thereby form the plurality of passages.3. The boron-coated neutron detector according to claim 2 , wherein each of the substrates is L-shaped which is formed by folding a planar substrate claim 2 , in such a way to provide each passage with a square cross section.4. The boron-coated neutron detector according to claim 2 , wherein each of the substrates contains at least one L-shaped step formed by folding a planar substrate claim 2 , in such a way to provide each passage with a ...

TRANSVERSE IN-CORE PROBE MONITORING AND CALIBRATION DEVICE FOR NUCLEAR POWER PLANTS, AND METHOD THEREOF

A method and apparatus for the calibration of neutron flux monitoring devices used in a nuclear reactor core. The apparatus includes a transverse in-core probe (TIP) cable with a neutron absorber located a fixed distance apart from a TIP detector. The neutron absorber may be passed within close proximity of the neutron flux monitoring device such that a perceived drop in measured neutron flux occurs, whereupon the cable may be repositioned relative to the monitoring device to ensure that the TIP detector is within close proximity of the monitoring device for purposes of calibrating the monitoring device. 17-. (canceled)8. A method of calibrating a monitoring device in a nuclear reactor comprising:passing a cable through a nuclear reactor core near the monitoring device, the cable including a neutron absorber, and a detector positioned a fixed distance apart from the neutron absorber;recording measurements from the detector and the monitoring device; andrecalibrating the monitoring device based on the recorded measurements from the detector and the monitoring device.9. The method of claim 8 , wherein the measurements taken from the detector include neutron flux or gamma flux measurements.10. The method of claim 8 , wherein the detector measurements and the monitoring device measurements are recorded as a function of distance traveled by the cable.11. The method of claim 10 , wherein the detector measurements and the monitoring device measurements are recorded at about every one inch of travel by the cable.12. The method of claim 10 , further comprising:determining the length of travel by the cable associated with a peak dip in monitoring device measurements;adding or subtracting the fixed distance to the determined length of travel by the cable to arrive at a cable-travel calibration-length; andrecording the detector measurement and the monitoring device measurement at the cable-travel calibration-length.13. The method of claim 12 , further comprising:calibrating the ...

Glass-panel lithium-6 neutron detector

A thermal neutron detector includes a planar detector housing having two glass panels spaced apart by a gas-tight seal defining a detection chamber including an inert detection gas and lithium foils adhered to inner surfaces of the glass panel(s). The lithium foils emit alpha particles and tritons in response to incident thermal neutrons, and the inert detection gas is ionized by the particles to generate drift electrons. A planar array of detection wires is spaced apart from the lithium foils and extends outside the detection chamber. Electronic bias applies a field voltage between the wires and the lithium foils to establish a drift electric field in the detection chamber effective to attract the drift electrons to the wires and provide a large electric field near the anode wires to cause electron multiplication near the wire resulting in large numbers of electrons and positive ions for each initial electron. Detection circuitry detects electric signals in wires generated by the drift of positive ions away from the wires and interpret the electrical signals as incidence of thermal neutrons on the detector.

Method and System for Detecting Special Nuclear Materials

A method and system for detecting special nuclear materials are disclosed. Said method and system detect the special nuclear materials by making use of the photofission characteristic and thermal neutron induced fission characteristic thereof. In one preferred embodiment, the high density and/or high atomic number region in the object to be detected is also detected first as a suspicious region. 1. A system for detecting special nuclear materials , comprising:an electron beam source for producing first, second and third electron beams, respectively;an electronic target located such that the first, second and third electron beams bombard an electronic target to produce first, second and third X-ray beams, respectively;a beam splitter;an photoneutron conversion target movable between a working position and a non-working position;X/γ ray detector and neutron detector for detecting X/γ ray and neutron ray signals emitted and/or transmitted from the object to be detected;wherein, when an electron accelerator emits a third electron beam, the photoneutron conversion target is in a working position, the beam splitter splitting first part and second part from the third X-ray beam, the first part bombarding the photoneutron conversion target to produce a photoneutron beam; and the second part of the X-ray beam and the photoneutron beam being respectively used to carry out X-ray transmission detection and neutron transmission detection on the object to be detected;wherein, when the electron accelerator emits a first electron beam, the photoneutron conversion target is in a non-working position, the energy of the first electron beam being set such that the first X-ray beam enables the special nuclear materials that possibly exist in the object to be detected to undergo a photofission;wherein, when the electron accelerator emits a second electron beam, the photoneutron conversion target is in a working position, the second X-ray beam bombarding the photoneutron conversion target ...

GAS-TIGHT PACKAGING OF DETECTORS

An atomic particle detection assembly includes one or more detectors that detect atomic particles. The detectors are positioned within a first chamber having a first operating pressure. The atomic particle detection assembly includes a junction apparatus supporting the detectors. The junction apparatus defines a second chamber having a second operating pressure that is different from the first operating pressure. Sensing electronics are attached to the detectors and the sensing electronics are housed within the second chamber of the junction apparatus. 1. An atomic particle detection assembly including:one or more detectors configured to detect atomic particles, the detectors being positioned within a first chamber having a first operating pressure; anda junction apparatus supporting the detectors, the junction apparatus defining a second chamber having a second operating pressure that is different from the first operating pressure, wherein sensing electronics are operatively attached to the detectors and the sensing electronics are housed within the second chamber of the junction apparatus.2. The atomic particle detection assembly of claim 1 , wherein the junction apparatus includes a shoulder extending around one of the detectors.3. The atomic particle detection assembly of claim 2 , further including a sealing device positioned between the shoulder and the detector within the junction apparatus.4. The atomic particle detection assembly of claim 3 , wherein the sealing device contacts the shoulder and the detector to seal the detector and the junction apparatus.5. The atomic particle detection assembly of claim 1 , wherein the second operating pressure is higher than the first operating pressure.6. The atomic particle detection assembly of claim 1 , wherein the junction apparatus includes a first housing.7. The atomic particle detection assembly of claim 6 , wherein the first housing defines a portion of the second chamber such that the first housing is maintained ...

DEVICE FOR MEASURING THE AMOUNT OF BERYLLIUM IN A RADIOACTIVE OBJECT

A device for measuring an amount of beryllium in a radioactive object, including: a hollow cylinder of a first piece made of a material to thermalize neutrons emitted by the radioactive object and a metal piece to mitigate a dose rate on the radioactive object, the first piece having a hollow cylinder shape deprived of a wall fraction, the metal piece including a solid part inserted in a space which corresponds to the deprived wall fraction of the first piece and a recessed part which is an extension of the solid part and is accommodated within the wall of the first piece, in contact with the first piece; a gamma radiation source accommodated in an indentation of the recessed part of the metal piece; and at least one neutron detector placed in a bulk of the first piece. 113-. (canceled)14. A device for measuring an amount of beryllium in a radioactive object , comprising: a piece made of a material for thermalizing neutrons emitted by the radioactive object, and', 'a metal piece for mitigating a dose rate on the radioactive object,, 'a hollow cylinder comprisingthe piece of material for thermalizing neutrons having a hollow cylinder shape deprived of a wall fraction; a solid part inserted in a space that corresponds to the deprived wall fraction of the piece made of a material for thermalizing neutrons, and', 'a recessed part which extends away from the solid part and is accommodated within the wall of the piece made of a material for thermalizing neutrons, in contact with the piece made of a material for thermalizing neutrons;, 'the metal piece comprisinga gamma radiation source accommodated in an indentation of the recessed part of the metal piece; andat least one neutron detector placed in a bulk of the piece made of a material for thermalizing neutrons,and wherein, in a cross-section plane perpendicular to the axis of the cylinder, a distance which separates, in the piece made of a material for thermalizing neutrons, the metal piece of a neutron detector is ...

ACCELERATING FISSILE MATERIAL DETECTION WITH A NEUTRON SOURCE

A neutron detector system for discriminating fissile material from non-fissile material wherein a digital data acquisition unit collects data at high rate, and in real-time processes large volumes of data directly to count neutrons from the unknown source and detecting excess grouped neutrons to identify fission in the unknown source. The system includes a Poisson neutron generator for in-beam interrogation of a possible fissile neutron source and a DC power supply that exhibits electrical ripple on the order of less than one part per million. Certain voltage multiplier circuits, such as Cockroft-Walton voltage multipliers, are used to enhance the effective of series resistor-inductor circuits components to reduce the ripple associated with traditional AC rectified, high voltage DC power supplies. 1. A system for characterizing a radiation source as fissile material or non-fissile material , comprising:a neutron generator configured to irradiate the radiation source by inducing radiation in the radiation source;a detector configured to receive and count neutrons emitted from the radiation source; andan analyzer component coupled to the detector and configured to determine the number of times that a group of n simultaneously emitted neutrons is observed from the radiation source after a defined measurement time period is repeated a defined number of times to derive a neutron count measurement, subtract an expected number of pairs of neutrons emitted by a hypothetical non-fission Poisson neutron source embodied in the neutron generator during the measurement time period from the number of pairs of observed neutrons derived from the neutron count measurement; characterize the radiation source as fissile material if the number of pairs of observed neutrons exceeds the expected number of pairs of neutrons in at least a portion of a histogram derived for the Poisson neutron source as compared to a histogram derived for the neutron count measurement.2. The system of ...

OUT-OF-CORE NUCLEAR INSTRUMENTATION DEVICE

A detector signal-processing circuit comprises the following: a current/voltage conversion part that converts the current value of a neutron detector to a voltage value; a variable gain amplification part that performs amplification by a first-step variable gain using a D/A converter; a current level response-use resistance circuit that selects the measurement range in accordance with the voltage value; temperature measurement units for measuring the temperature of the resistance circuit for current level response; a temperature compensation part for commanding gain compensation by the D/A converter on the basis of the measured temperature; and a selective adjustment control part for selective control of the measurement range and adjustment of the variable gain of the variable gain amplification part. Due to this configuration, neutron flux can be measured with high precision while maintaining a constant output precision, before and after switching of the measurement range. 1. An out-of-core nuclear instrumentation device comprising:a detector signal-processing circuit that converts neutron flux leaking from a nuclear reactor vessel into a current value and performs a measurement processing on the neutron flux, the neutron flux being detected by a neutron detector disposed outside the nuclear reactor vessel,wherein the detector signal-processing circuit is configured to includea current/voltage conversion part that converts the current value into a voltage value,a variable gain amplification part that amplifies the voltage value with a variable gain by a D/A converter,a measurement range selection part that is provided in the current/voltage conversion part or the variable gain amplification part and selects a measurement range according to the current value,a temperature measurement unit that measures a temperature of the measurement range selection part,a temperature compensation part that outputs a gain compensation value to the D/A converter based on the ...

NEUTRON MEASUREMENT APPARATUS, NEUTRON CALCULATION APPARATUS, AND NEUTRON MEASUREMENT METHOD

According to an embodiment, a neutron measurement apparatus has: a neutron detector; a gamma ray detector; a neutron detector signal processing unit which performs Fourier transform on the signals received for a prescribed period, generates neutron detector signal frequency data in a frequency domain, calculates the neutron-detection signal power spectrum and stores it; a gamma-ray detector signal processing unit which performs Fourier transform on the signals received for a prescribed period, generates gamma ray detector signal frequency data in a frequency domain, calculates gamma ray detector signal power spectrum and stores it; and a neutron calculation unit which generates a neutron signal by removing a part contributed by the gamma ray detector signal power spectrum from the neutron detector signal power spectrum. 1. A neutron measurement apparatus comprising:a neutron detector configured to measure neutrons;a gamma ray detector configured to measure gamma rays;a neutron detector signal processing unit configured to receive signals from the neutron detector sequentially, to perform Fourier transform on the signals received for a prescribed period, to generate neutron detector signal frequency data in a frequency domain, thereby to calculate the neutron-detection signal power spectrum and to store the neutron detector signal power spectrum;a gamma-ray detector signal processing unit configured to receive signals from the gamma ray detector sequentially, to perform Fourier transform on the signals received for a prescribed period, to generate gamma ray detector signal frequency data in a frequency domain, thereby to calculate gamma ray detector signal power spectrum and to store the gamma ray detector signal power spectrum; anda neutron calculation unit configured to generate a neutron signal by removing a part contributed by the gamma-ray-detector signal power spectrum from the neutron detector signal power spectrum.2. The neutron measurement apparatus ...

METHOD OF DEPOSITING BORON ON SHEET METAL FOR NEUTRON DETECTION APPARATUS OR IONIZATION CHAMBER

The invention is a method of depositing a solid layer () of boron on a metal support () intended for a neutron detection apparatus () characterized in that it comprises at least one step of depositing at least one layer () comprising boron on the metal support () and a step of cold-pressing of the metal support () with the layer () comprising boron. 1123012323110123. A method of depositing a solid layer () of boron on a metal support ( , ) intended for a neutron detection apparatus () or an ionization chamber , wherein the method comprises at least a step of depositing at least one layer () comprising boron in the form of nanoparticles onto the metal support ( , ) and a step of cold pressing the metal support ( , ) with the boron comprising layer () , the proportion of boron (B) in the layer () deposited onto the metal support ( , ) being between 80% and 100%.223. The method as claimed in claim 1 , wherein the deposition step is preceded by a step of prepressing the metal support ( claim 1 , ).3. The method as claimed in claim 1 , wherein:{'b': 1', '2', '3', '2', '3', '2', '3', '2', '3', '2', '3, 'the step of depositing at least one boron comprising layer () onto the metal support (, ) is a step of depositing boron nanoparticle (BNP)-based ink onto the metal support (, ); the step of depositing BNP-based ink onto the metal support (, ) being followed by a step of drying the metal support (, ) onto which ink has been deposited to leave only the BNP and the dispersant on the metal support (, );'}{'b': 2', '3', '2', '3', '2', '3', '2', '3', '1', '2', '3, 'the step of cold pressing the metal support (, ) is carried out on the metal support (, ) with the BNP and the dispersant left on the metal support (, ); the step of cold pressing the metal support (, ) with the boron-comprising layer () being optionally preceded or followed by a step of cooking the metal support (, ) in order to evaporate water fixed in the pores of the BNP and to incinerate or calcine the dispersant ...

NEUTRON DETECTION APPARATUS

Provided are a neutron detector detecting a neutron flux distribution of the inside of a reactor, a thimble guide tube provided being inserted from outside into inside of the reactor, for inserting the neutron detector, a drive apparatus connected to the thimble guide tube and inserting or extracting the neutron detector into or out of the thimble guide tube, a vacuum unit controlling the vacuum state in the thimble guide tube, a supply unit supplying carbon dioxide gas, a gas purge unit connected to the supply unit and conducting gas purge in the thimble guide tube by carbon dioxide gas, a gate valve provided between the thimble guide tube and the drive apparatus and performing open/close operation, and a control apparatus controlling the gate valve, the drive apparatus, the vacuum unit, the supply unit, and the gas purge unit. 1. A neutron detection apparatus which detects a neutron flux distribution of the inside of a pressurized water reactor , the neutron detection apparatus comprising:a neutron detector which detects the neutron flux distribution of the inside of the reactor;a thimble guide tube which is provided being inserted from the outside of the reactor into the inside of the reactor, for inserting the neutron detector into the inside of the reactor;a drive apparatus which is connected to the thimble guide tube and which inserts the neutron detector into the thimble guide tube or extracts the neutron detector out of the thimble guide tube;a vacuum unit which controls the vacuum state in the thimble guide tube;a supply unit which supplies carbon dioxide gas;a gas purge unit which is connected to the supply unit and conducts gas purge in the thimble guide tube by carbon dioxide gas;a gate valve which is provided between the thimble guide tube and the drive apparatus and performs open/close operation between the thimble guide tube and the drive apparatus; anda control apparatus which controls the gate valve, the drive apparatus, the vacuum unit, the supply ...

Air Slide Analyzer System and Method

Systems and Methods for an air slide analyzer for measuring the elemental content of aerated material traveling by air slide. The air slide analyzer has an analyzer having an entrance opening and an exit opening, and an interior tunnel adapted for aerated material conveyed by an air slide; a radiation detector proximal to the analyzer; a neutron source emitting neutrons into material within the analyzer; and a processor to analyze detected information from the radiation detector, wherein emissions from the material being irradiated with neutrons are detected by the radiation detector and analyzed by the processor to provide elemental information of the material in the analyzer. 1. An air slide analyzer for measuring the elemental content of aerated material traveling by air slide , the air slide analyzer comprising:an analyzer having an entrance opening and an exit opening, and an interior tunnel adapted for aerated material conveyed by an air slide;an air slide adjacent to the tunnel;a radiation detector proximal to the analyzer;a source of neutrons emitting neutrons into material within the analyzer;a processor to analyze detected information from the radiation detector, wherein emissions from the material being irradiated with neutrons are detected by the radiation detector and analyzed by the processor to provide elemental information of the material in the analyzer; anda mechanism for increasing a mass per length of material of the material above a mass level per length flowing in a standard air slide section without an analyzer.2. The air slide analyzer of claim 1 , wherein the analysis is at least one of prompt gamma neutron activation analysis (PGNAA) claim 1 , Thermal Neutron Analysis (TNA) claim 1 , Pulsed Fast Neutron Analysis (PFNA) claim 1 , Pulsed Thermal Neutron Analysis (PTNA) claim 1 , Pulsed Fast Thermal analysis (PFTNA) and Fast Neutron Analysis (FNA).3. The air slide analyzer of claim 1 , further comprising a complimentary measurement system ...

NEUTRON GRID, NEUTRON GRID STACK, NEUTRON GRID DEVICE, AND METHOD OF MANUFACTURING NEUTRON GRID

A neutron grid, comprises: a grid including: a plurality of spacers through which at least a part of first neutrons from a target passes; and a plurality of absorbers to absorb at least a part of second neutrons scattered thorough the target, the spacers and the absorbers being alternately arranged along a first direction and extending along a second direction intersecting with the first direction; and a pair of covers through which at least a part of the first neutrons and at least a part of the second neutrons pass, sandwiching the grid along a third direction intersecting with the first and second directions. A thermal expansion coefficient difference between one of the spacers and one of the absorbers is ±9×10/° C. or less, or Young's modulus of the spacer is 100 GPa or more. 1. A neutron grid , comprising:a grid including: a plurality of spacers through which at least a part of first neutrons from a target passes; and a plurality of absorbers to absorb at least a part of second neutrons scattered thorough the target, the spacers and the absorbers being alternately arranged along a first direction and extending along a second direction intersecting with the first direction; anda pair of covers through which at least a part of the first neutrons and at least a part of the second neutrons pass, sandwiching the grid along a third direction intersecting with the first and second directions,{'sup': '−6', "wherein a thermal expansion coefficient difference between one of the spacers and one of the absorbers is ±9×10/° C. or less, or Young's modulus of one of the spacers is 100 GPa or more."}2. The neutron grid according to claim 1 , wherein{'sup': '−6', "the thermal expansion coefficient difference is ±9×10/° C. or less, and the Young's modulus of one of the spacers is 100 GPa or more."}3. The neutron grid according to claim 1 , whereinthe first neutrons and the second neutrons include thermal neutrons.4. The neutron grid according to claim 3 , whereina thermal ...

FILM DOSIMETER AND METHOD OF DETERMINING RADIATION DOSE USING THEREOF

A film dosimeter is disclosed in the present invention and doped with a sensitizer for determining a neutron and gamma-ray mixed radiation field. The sensitizer comprises quantitative lithium atoms with a different atom percentage of lithium-6 and lithium-7. Theoretically, the atom percentage of the lithium-6 in the lithium atoms is ranged from 0.1 to 99. On the other hand, a method of determining radiation doses of a neutron and gamma-ray mixed radiation field by using the abovementioned film dosimeter is also disclosed in the present invention. 1. A sensitizer of a film dosimeter for detecting a neutron dose of a mixed radiation field comprising quantitative lithium atoms , wherein the lithium atoms comprise different atom percentage of lithium-6 (Li) and lithium-7 (Li) , and an atom percentage of Li in the lithium atoms is ranged from 0.1 to 99.2. The sensitizer according to claim 1 , wherein the mixed radiation field is a neutron and gamma-ray radiation mixed field.3. The sensitizer according to further being doped with quantitative hydrogen elements (H) to decrease the neutron kinetic energy for detecting the fast neutron dose.4. A film for detecting a dose of a mixed radiation field claim 1 , comprising:a base;{'claim-ref': {'@idref': 'CLM-00001', 'claim 1'}, 'an active layer being placed on the base and doped with the sensitizer provided according to ;'}a surface layer being placed on the active layer;an adhesive being placed on the surface layer; anda top covering on the adhesion layer.5. The film according to claim 4 , wherein the sensitizer can be further doped in an area of 10 μm above and 10 μm below the active layer.6. The film according to claim 4 , wherein the film can be combined with films with different sensitivity to form a dosimeter.7. The film according to claim 6 , wherein the films with different sensitivity is thermal neutron sensitizing films or thermal neutron desensitizing films.8. The film according to claim 7 , wherein the thermal ...

Integrated Primary and Special Nuclear Material Alarm Resolution

The present specification discloses methods for inspecting an object. The method includes scanning an object in a two-step process. In the primary scan, a truck or cargo container (container) is completely scanned with a fan beam radiation, the transmitted radiation is measured with an array of detectors, and the transmission information and optionally the fission signatures are analyzed to determine the presence of high-density, high-Z and fissionable materials. If the container alarms in one or more areas, the areas are subjected to a secondary scan. This is done by precisely repositioning the container to the location of the suspect areas, adjusting the scanning system to focus on the suspect areas, performing a stationary irradiation of the areas, and analyzing the measured feature signatures to clear or confirm the presence of SNM. 1. An inspection system for inspecting an object using radiation comprising:an X-ray source for generating and transmitting X-ray radiation;a collimator positioned in front of said X-ray radiation source wherein said collimator comprises two vertical structures defining a vertical slit through which said transmitted X-ray radiation is directed and a plurality of horizontally movable members positioned in front of said vertical slit, wherein said plurality of horizontally movable members each have a first configuration where they block more of the transmitted radiation from passing through the vertical slit and a second configuration where they block less of the transmitted radiation from passing through the vertical slit;a detector array for detecting a portion of transmitted radiation passing through said object; anda controller, wherein said controller is programmed to cause at least a portion of said horizontally movable members to move depending upon a mode of operation.2. The inspection system of wherein said mode of operation is a first stage scanning mode and wherein claim 1 , in response to the first stage scanning mode claim ...

PORTABLE RADIATION DETECTION SYSTEM

A hand-held portable radiation detection device, such as a radiation isotopic identification device (RIID), is integrated with a personal digital assistant device (PDA), such as a smart phone, to provide with improved data processing capability and user interface. The PDA is configured to receive and process data received from the radiation detection device. 1. A portable radiation detection system , comprising: at least one radiation detector configured to detect radiation and generate electronic signals;', 'a first signal processing unit configured to process the electronic signals and generate digitized data;', 'a first communication unit configured to transmit the digitized data;', 'wherein the at least one radiation detector, the first signal processing unit, and the first communication unit are housed in an outer casing;, 'a radiation detection subsystem including a second signal processing unit configured to process the digitized data received from the radiation detection subsystem;', 'a user interface unit;', 'a second communication unit configured to communicate with the first communication unit to receive the digitized data;, 'a personal digital assistant (PDA) includinga mounting unit attached to the outer casing and configured to hold the PDA, and wherein the outer casing includes a recessed portion configured to receive the PDA therein in a closed position, wherein the mounting unit includes a hinge, a holder, and an attachment element, wherein the holder is attached to one end of the hinge, and the outer casing is attached to the opposite end of the hinge via the attachment element, wherein the holder is configured to hold the PDA.2. The portable radiation detection system of claim wherein the at least one radiation detector includes a gamma-ray detector having gamma-ray spectroscopic radiation measurement capability , a gas tube based gamma detector for measuring high count-rate gamma-ray radiation , and a neutron detector for measuring neutron ...

SYSTEM AND METHOD FOR INTERNAL INSPECTION OF RAIL COMPONENTS

An internal imaging system has a radiation source and a plurality of detectors positioned to receive portions of the plurality of collimated beams that have been attenuated by interaction with the target. The radiation source is configured to irradiate a target with a plurality of collimated beams of radiation. Two of the plurality of collimated beams of radiation may have different beam shapes. Another internal imaging system includes a radiation source configured to irradiate a target with at least one collimated beam of radiation and at least one detector. A planar rotating collimator is positioned adjacent to the radiation source and is configured to form the at least one collimated beam. The at least one detector is positioned to receive attenuated portions of the at least one collimated beam. The radiation source may be or include a neutron source. The detectors may be or include a plurality of neutron converters. 1. An internal imaging system , the system comprising:a radiation source configured to irradiate a target with a plurality of collimated beams of radiation, wherein two of the plurality of collimated beams of radiation have different beam shapes; anda plurality of detectors, the detectors positioned to receive portions of the plurality of collimated beams that have been attenuated by interaction with the target.2. The system of claim 1 , wherein the radiation source and the plurality of detectors are mounted upon a vehicle.3. The system of claim 2 , wherein the vehicle is a rail traversing vehicle.4. The system of claim 1 , wherein the radiation source comprises a neutron source and the plurality of detectors includes at least one neutron converter.5. The system of claim 1 , wherein the plurality of collimated beams includes a rotating pencil beam and at least one fan beam6. The system of claim 5 , wherein the at least one fan beam is a plurality of fan beams.7. The system of claim 6 , wherein the rotating pencil beam is positioned between two of the ...

EX-CORE NUCLEAR INSTRUMENTATION DEVICE

A detector signal processing circuit is composed of a current/voltage converting unit which converts the current value, which is converted by a neutron detector, to a voltage value which corresponds to the current value; a variable gain amplifying unit which includes an operating amplifier, in which a D/A converter is added, and amplifies the voltage value which is converted by the current/voltage converting unit; a regulation control means which regulates a gain of the D/A converter; and a comparator which automatically compares an output voltage, which is amplified by the variable gain amplifying unit, in accordance with a reference value which is previously set, so as to output the output voltage to the regulation control means. 16-. (canceled)7. An ex-core nuclear instrumentation device comprising:a neutron detector for measuring a neutron beam at the outside of a nuclear reactor vessel and converting the neutron beam to a current value; and a current/voltage converting unit which converts the current value converted by the neutron detector to a voltage value corresponding to the current value;', 'a variable gain amplifying unit having an operating amplifier, in which a D/A converter is included, and amplifying the voltage value converted by the current/voltage converting unit;', 'a regulation controller which regulates a gain of the D/A converter; and', 'a comparator for comparing an output voltage amplified by the variable gain amplifying unit with a reference value previously set, and outputting its output voltage to the regulation controller., 'an ex-core nuclear instrumentation board for computing and processing the current value from the neutron detector by using a detector signal processing circuit so as to output a state of the neutron beam when a nuclear reactor is operated; wherein the detector signal processing circuit includes8. An ex-core nuclear instrumentation device according to claim 7 , the detector signal processing circuit including:the ...

Ion Chamber Radiation Detector

An in-core nuclear detector for detecting the neutron population surrounding the detector. The detector is an ion chamber having a cylindrical outer electrode that is insulated from a central electrode and capped to contain an Argon gas. An electron radiator that produces prompt neutron capture gamma radiation that is substantially, directly proportional to the local neutron population is disposed between the outer tubular electrode and the central electrode. 1. An ion chamber radiation detector with enhanced fission gamma radiation response comprising:an outer tubular electrode having an upper and lower end;a lower electrically insulated end cap closing of the lower end of the outer tubular electrode;an upper electrically insulated end cap closing off the upper end of the outer tubular electrode;a central electrode extending substantially from the lower end cap up and through the upper end cap; andan electron radiator that produces prompt neutron capture gamma radiation that is substantially, directly proportional to the local neutron population disposed between the outer tubular electrode and the central electrode.2. The ion chamber radiation detector of wherein the electron radiator is constructed from a material having a high Z value with which prompt neutron capture gamma radiation interacts with through photoelectric and Compton scattering mechanisms.3. The ion chamber radiation detector of wherein the electron radiator is constructed from one or more materials selected from a group of metals comprising platinum claim 1 , gold claim 1 , manganese claim 1 , tungsten and cadmium.4. The ion chamber radiation detector of wherein the electron radiator is mainly constructed from a group of metals comprising manganese claim 1 , tungsten and cadmium.5. The ion chamber radiation detector of wherein the electron radiator is at least partially coated with either or both platinum or gold.6. The ion chamber radiation detector of including a plurality of electron radiators ...

METHOD OF VALIDATING NUCLEAR REACTOR IN-VESSEL DETECTOR OUTPUT SIGNALS

A method to perform signal validation for either reactor fixed incore detectors and/or core exit thermocouples to enhance core monitoring systems. The method uses a combination of both measured sensor signals and expected signal responses to develop a ratio of measured to expected signals. The ratios are evaluated by determining the expected ratios for each detector based on the behavior of the remaining collection of detectors, taking into account the geometry/location of the other detectors. The method also provides for automatic removal of invalid detectors from the core power distribution determination if sufficient detectors remain on line to adequately characterize the core's power distribution. 1. A method of validating a nuclear reactor instrumentation output signal for a plurality of in-reactor detectors having a plurality of detector elements radially spaced at approximately the same axial elevation relative to a nuclear reactor core with each of the detector elements having an output signal indicative of a measured reactor operating parameter at a radial and axial location at which the detector element is located , comprising the steps of:running a predictive calculation of an anticipated output of three or more of the detector elements at substantially the same axial elevation based on a current operating state of the reactor;taking a ratio of an actual signal respectively generated by the three or more detector elements at approximately the same axial elevation, to the corresponding anticipated output;generating an expected range of the ratios of the actual signals generated to the corresponding anticipated outputs for a number of adverse plant operating conditions;determining if the ratio of the actual signal generated by any of the three or more of the detector elements at substantially the same axial elevation is outside the range of ratios;spline fitting the ratios of the detector elements at substantially the same axial elevation that are within ...

Radiation-monitoring system with correlated hodoscopes

At least one pair of hodoscope radiation monitors arranged to simultaneously monitor a target region that contains a source of radiation. The hodoscopes are preferably arranged so that their fields of view of the region are approximately orthogonal. The fields of view of the two detectors will overlap in a region that contains the source of radiation. Each of the two detectors will record radiation from the overlap region and, in addition, will record background radiation emanating from other regions within detector fields of view. The present invention provides statistical correlation techniques to estimate the extent to which unusually high radiation originates in the overlap region, irrespective of background in the field-of-view of individual hodoscope detectors. The source of radiation might be spontaneous, might be from an activation process, or might be scattered in from an external beam. 1. A radiation-monitoring diagnostic hodoscope system for monitoring or measuring a radiation source or radiation sources from a target location , said system comprising: 1) being adapted to detect gamma or neutron or gamma and neutron radiation in a limited radiation beam of less than 50 degrees defining a field of view and', 'and comprising:', '2) being positioned so that their beams overlap in a region containing all or a part of the target location,'}, '1) a collimating means adapted to identify said limited radiation beam and', '2) at least one radiation detector adapted to produce electrical signals corresponding to intensities of gamma and or neutron radiation in said limited radiation beam;, 'A) at least one pair of radiation-monitoring hodoscope units, each unit of each pairB) a computer processor programmed with an algorithm adapted examine the data recorded by the at least two hodoscope units so as to determine the correlation of the recorded data so as to estimate the extent to which the radiation source or sources originate in the overlap region.2. The system as ...

DISCHARGE APPARATUS USABLE FOR DETERMINING NEUTRON FLUX

A discharge apparatus usable in a nuclear reactor includes an emitter apparatus in the form of a plurality of wire segments that emit electrons via beta decay to a collector. The rate at which the electrons are emitted is directly related to the neutron flux in the vicinity of each wire segment. The continual emission of electrons from the wire segments to the collector results in a charge imbalance, and an electrostatic discharge event in the form of a spark occurs between the wire segment and the collector. Time-of-flight techniques are used to analyze signals that result from the electrostatic discharge event to determine the position along the discharge apparatus where the electrostatic discharge event occurred. The electrostatic discharge events over time at various locations along the discharge apparatus where the wire segments are situated are employed in determining the neutron flux and thus the power generation at the locations. 1. A discharge apparatus usable in a nuclear reactor environment for determining neutron flux at a plurality of locations and being structured to be connected with a number of inputs of a detection device , the discharge apparatus comprising:an elongated emitter apparatus comprising a plurality of emitters spaced apart from one another in a predetermined fashion along the longitudinal extent of the emitter apparatus, the plurality of emitters each being structured to emit a number of electrons via beta decay responsive to its absorption of neutrons;a collector situated in proximity to the emitter apparatus and being structured to collect from the plurality of emitters the number of electrons;an insulator apparatus interposed between the emitter apparatus and the collector, the insulator apparatus electrically insulating from one another at least some of the emitters of the plurality of emitters;the emitter apparatus and the collector being electrically insulated from one another due at least in part to the insulator apparatus; andat ...

REACTOR INSTRUMENTATION SYSTEM AND REACTOR

An object of the invention is to provide a reactor instrumentation system that can be easily repaired or replaced. The invention includes: an instrumentation tube provided in a reactor core; a gas flow pipe provided in the instrumentation tube; a suction mechanism for supplying gas containing oxygen to the gas flow pipe; and a nuclide analysis device for measuring a nuclide in the gas in the gas flow pipe. According to the invention, it is possible to provide a reactor instrumentation system that can be easily repaired or replaced. 1. A reactor instrumentation system for monitoring a state of a reactor , comprising:an instrumentation tube provided in a reactor core;a gas flow pipe provided in the instrumentation tube;a suction mechanism for supplying gas containing oxygen to the gas flow pipe; anda nuclide analysis device for measuring a nuclide in the gas in the gas flow pipe.2. The reactor instrumentation system according to claim 1 , whereinthe nuclide analysis device is provided to measure gamma rays emitted from N-16 in the gas flow pipe.3. The reactor instrumentation system according to claim 1 , whereinthe nuclide analysis device is provided to measure gamma rays emitted from O-19 in the gas flow pipe.4. The reactor instrumentation system according to claim 2 , further comprisinga monitoring device for monitoring reactor power on the basis of a measurement result transmitted from the nuclide analysis device.5. The reactor instrumentation system according to claim 2 , whereinthe gas flow pipe is provided to be adjacent to a neutron detector for a local power range monitor, and sensitivity of the neutron detector for a local power range monitor is calibrated on the basis of a measurement result from the nuclide analysis device.6. The reactor instrumentation system according to claim 2 , whereinthe gas flow pipe includes a plurality of pipes that are different in length, the pipes are arranged in the same instrumentation tube, and gamma rays emitted from the ...

DEVICE FOR PROCESSING SIGNALS DETECTED BY NEUTRON DETECTORS AND ASSOCIATED CONTROL/COMMAND DEVICE

A device for processing signals detected by a set of n neutron detectors, the device including: n switches each including an input and an output, each switch receiving, on its input, a detected signal coming from a different detector, outputs of the n switches being linked to each other; and a clock generator including a clock circuit and a sequential counter controlled by the clock circuit and configured to deliver a plurality of pulse series, each pulse series of the plurality of pulse series constituting a control signal of a different switch, the pulses of any two pulse series of the plurality of pulse series being disjointed. 15-. (canceled)6. A device for processing signals detected by a set of n neutron detectors , the device comprising:n switches each including an input and an output, each switch receiving, on its input, a detected signal coming from a different detector, outputs of the n switches being linked to each other; anda clock generator including a clock circuit and a sequential counter controlled by the clock circuit and configured to deliver a plurality of pulse series, each pulse series of the plurality of pulse series constituting a control signal of a different switch, the pulses of any two pulse series of the plurality of pulse series being disjointed.7. The device according to claim 6 , further comprising means for widening the width of pulses of at least one first pulse series relative to the width of pulses of at least one second pulse series.8. The device according to claim 6 , further comprising means for insulating the switches against a high supply DC voltage of the neutron detectors.9. A device for controlling/commanding a nuclear reactor core which includes a plurality of neutron detectors claim 6 , comprising a device for processing the detected signals according to .10. A device for controlling/commanding a nuclear reactor core which includes a plurality of neutron detectors claim 7 , comprising a device for processing the detected ...

Neutron spectrometer

A neutron spectrometer that is more accurate, faster, and more-portable than conventional spectrometers includes an organic scintillator responsive to neutrons and gammas and an inorganic scintillator that captures neutrons. A processor receives signals representative of scintillations in the organic scintillator and in the inorganic scintillator and discriminates neutron signals from gamma signals. The processor also determines pulse areas for neutron moderating signals and performs unfolding based on the determined pulse areas to produce a neutron energy spectrum and/or dose information.

RADIATION DETECTION DEVICE AND RADIATION DETECTION METHOD

According to an embodiment, a radiation detection device includes one or more processors. The one or more processors are configured to: acquire an output waveform, from a detector configured to output the output waveform according to radiation; and identify a type of radiation incident on the detector, based on a first integrated value of the output waveform in a first integration period and a second integrated value of the output waveform in a second integration period. 1. A radiation detection device comprising:one or more processors configured to:acquire an output waveform, from a detector configured to output the output waveform according to radiation; andidentify a type of radiation incident on the detector, based on a first integrated value of the output waveform in a first integration period and a second integrated value of the output waveform in a second integration period, whereinthe first integration period and the second integration period have the same period start timing and have different period lengths in the output waveform, andthe period start timing is one of timing that matches with a peak in the output waveform and timing after the peak.2. (canceled)3. The device according to claim 1 , wherein the one or more processors are further configured to determine the period start timing of the first integration period and the second integration period in the output waveform.4. The device according to claim 1 , wherein the first integration period and the second integration period include timing corresponding to a peak of the output waveform.5. The device according to claim 1 , wherein the one or more processors are configured to identify the type of radiation using a ratio of the first integrated value and the second integrated value.6. The device according to claim 1 , wherein the one or more processors are configured to identify the type of radiation using a feature amount of a map representing a relation between the first integrated value and the ...

PULSED NEUTRON AZIMUTHAL MEASUREMENT SYSTEM AND METHOD

Embodiments of the present disclosure include a downhole inspection system including a neutron generation unit operable to emit neutrons toward a target in a wellbore. The system also includes a neutron detection unit fixed relative to the neutron generator and operable to detect thermal neutrons from the target. The system includes a shielding arrangement forming at least a portion of the neutron detection unit, the shielding arrangement blocking at least a portion of the thermal neutrons, from penetrating beyond a predetermined radial location within the neutron detection unit. 1. A downhole inspection system , comprising:a downhole tool string lowerable into a wellbore; a neutron generator operable to emit neutrons toward a target;', 'a plurality of neutron detectors fixed relative to the neutron generator, each neutron detector of the plurality of neutron detectors arranged equidistant from the neutron generator, and operable to detect backscattered neutrons from the target; and', 'a shielding arrangement to absorb thermal neutrons positioned between adjacent neutron detectors of the plurality of neutron detectors, the shielding arrangement positioned to establish azimuthal sensitivity for the respective detectors., 'a neutron imaging device forming at least a portion of the downhole tool string, the neutron imaging device operable to generate neutron imaging data for detecting a wellbore characteristic, wherein the neutron imaging device comprises2. The downhole inspection system of claim 1 , wherein the plurality of neutron detectors are arranged symmetrically relative to a longitudinal axis of the neutron imaging device and symmetrically relative to a lateral axis of the neutron imaging device.3. The downhole inspection system of claim 1 , wherein the shielding arrangement comprises panels extending from a top of the plurality of neutron detectors to a bottom of the plurality of neutron detectors.4. The downhole inspection system of claim 1 , wherein the ...

HE-3 DETECTOR GUARD BAND

A neutron detector for detecting neutrons includes an exterior shell bounding and sealing an interior volume. The exterior shell serves as a cathode. A central structure extends longitudinally within the exterior shell. The central structure serves as an anode and is maintained at a first voltage. The neutron detector includes an insulating portion extending between the central structure and the exterior shell and longitudinally past a shell end of the exterior shell towards a structure end of the central structure. A guard structure extends circumferentially around an outer insulating surface. The guard structure is positioned on the insulating portion between the shell end and the structure end. The guard structure is maintained at a second voltage such that a leakage current on the outer insulating surface is absorbed by the guard structure. A method of detecting neutrons with the neutron detector is also provided. 1. A neutron detector for detecting neutrons , the neutron detector including:an exterior shell bounding and sealing an interior volume, the exterior shell serving as a cathode;a central structure extending longitudinally within the exterior shell, the central structure serving as an anode and being maintained at a first voltage;an insulating portion extending radially between the central structure and the exterior shell, the insulating portion extending longitudinally past a shell end of the exterior shell towards a structure end of the central structure; anda guard structure extending circumferentially around an outer insulating surface of the insulating portion, the guard structure being positioned on the insulating portion between the shell end and the structure end, wherein the guard structure is maintained at a second voltage such that a leakage current on the outer insulating surface of the insulating portion is absorbed by the guard structure.2. The neutron detector of claim 1 , wherein the central structure extends beyond the shell end of the ...

FISSION METER AND NEUTRON DETECTION USING POISSON DISTRIBUTION COMPARISON

A neutron detector system and method for discriminating fissile material from non-fissile material wherein a digital data acquisition unit collects data at high rate, and in real-time processes large volumes of data directly into information that a first responder can use to discriminate materials. The system comprises counting neutrons from the unknown source and detecting excess grouped neutrons to identify fission in the unknown source. Comparison of the observed neutron count distribution with a Poisson distribution is performed to distinguish fissile material from non-fissile material. 17-. (canceled)8. An apparatus for determining whether a radiation source has the characteristic of fission , comprising:a multiplicity counter counting neutrons emitted from the radiation source during a defined measurement time period, and determining the number of times that a group of n simultaneously emitted neutrons is observed from the radiation source after the measurement time period is repeated a defined number of times to derive a neutron count measurement;a difference calculator subtracting an expected number of pairs of neutrons emitted by a hypothetical non-fission Poisson neutron source during the measurement time period from the number of pairs of observed neutrons derived from the neutron count measurement to provide a calculated result, and determining if the number of pairs of observed neutrons exceeds the expected number of pairs of neutrons by a defined error range for each subtraction of the expected number of pairs of neutrons from the observed number of pairs of neutrons, wherein the defined error range represents a statistical measure that is indicative of fission by the observed neutrons;an analysis component producing a histogram representing the number of times different group sizes occur from a number of measurement time periods, and deriving a Poisson count distribution for the Poisson neutron source; anda graphing component overlaying the histogram ...

BORON COATED STRAWS FOR NEUTRON DETECTION WITH PIE-SHAPED CROSS-SECTION

A boron coated straw detector for use in a neutron detection system is disclosed comprising a boron coated straw having at least one boron-coated septum radially oriented and extending a pre-determined distance towards the center of the straw. Preferably, the straw comprises a plurality of septa comprising a rigid surface, coated on both sides with a boron composition. Preferably, the septa run the length of the straw detector from one end of the straw to the other. The area coated on the septa adds to the area coated on the arc segments offering a significant benefit in sensitivity of the neutron detector. 1. An improved boron-coated straw detector system comprising a boron-coated straw having a diameter and at least one septum extending radially inward from inner surface of the straw , each septum having a boron-coating on two sides and a length of about 0.25 times the straw diameter or less.2. The straw detector system of claim 1 , wherein the straw comprises a plurality of septa.3. The straw detector system of claim 1 , wherein each septum is within about 5% difference in length.4. The straw detector system of wherein the straw comprises an even number of septa.5. The straw detector system of claim 2 , wherein each septum extends from a first end of the straw to a second opposite end of the straw.6. The straw detector system of claim 2 , wherein the straw comprises 6 to 12 septa.7. The straw detector system of claim 6 , wherein the septa are equally spaced apart around the interior surface of the straw.8. The straw detector system of claim 7 , wherein the length of each septum is within about 5% of the length of an arc length between each septum.9. The straw detectors system of claim 7 , wherein the length of each septum is between about 50% and 100% of an arch length between each septum.10. A neutron detection system comprising a plurality of boron-coated straws formed into a panel claim 7 , each boron-coated straw in the panel having a plurality of septa ...

NEUTRON FLUX MAPPING SYSTEM AND CONTROL METHOD FOR NEUTRON FLUX MAPPING SYSTEM

Provided are a neutron detector for detecting a neutron flux distribution of the inside of a reactor, a drive cable connected to the neutron detector, a drive unit for driving the drive cable, a plurality of guide thimbles provided being inserted from the outside of the reactor into the reactor, for inserting the neutron detector, a storage tube for storing the neutron detector, a path transfer device connected to the drive unit, for selecting one of insertion of the neutron detector into each of the guide thimbles and insertion of the neutron detector into the storage tube, and an inspection guide tube connecting the drive unit and the storage tube. The drive unit has a switching unit for switching between the path transfer device side and the inspection guide tube side. 1. A neutron flux mapping system placed inside a containment vessel , for detecting a neutron flux distribution of the inside of a reactor , the neutron flux mapping system comprising:a neutron detector for detecting the neutron flux distribution of the inside of the reactor;a drive cable connected to the neutron detector, for moving the neutron detector;a drive unit for driving the drive cable;a plurality of guide thimbles provided being inserted from the outside of the reactor into a plurality of sections inside the reactor, for respectively inserting the neutron detector into the plurality of sections inside the reactor;a storage tube for storing the neutron detector outside the reactor;a path transfer device connected to the drive unit, for selecting one of insertion of the neutron detector into each of the guide thimbles and insertion of the neutron detector into the storage tube;a storage guide tube connecting the path transfer device and the storage tube; andan inspection guide tube connecting the drive unit and the storage tube, whereinthe drive unit has a switching unit for switching a path to one of the path transfer device side and the inspection guide tube side.2. The neutron flux ...

SELF-POWERED IN-CORE DETECTOR ARRANGEMENT FOR MEASURING FLUX IN A NUCLEAR REACTOR CORE

A self-powered in-core detector arrangement for measuring flux in a nuclear reactor core includes a first in-core detector and a second in-core detector. The first in-core detector includes a first flux detecting material, a first lead wire extending longitudinally from a first axial end of the first flux detecting material, a first insulating material surrounding outer diameters of the first flux detecting material and the first lead wire and a first sheath surrounding the first insulating material. The first sheath includes a first section surrounding the first flux detecting material and a second section surrounding the first lead wire. The first section of the first sheath has a greater outer diameter than the second section of the first sheath. The second in-core detector includes a second flux detecting material, a second lead wire extending longitudinally from a first axial end of the second flux detecting material, a second insulating material surrounding outer diameters of the second flux detecting material and the second lead wire, and a second sheath surrounding the second insulating material. The second sheath includes a first section surrounding the second flux detecting material and a second section surrounding the second lead wire. The first section of the second sheath has a greater outer diameter than the second section of the second sheath. The first section of the first sheath is axially offset from the first section of the second sheath and radially aligned with the second section of second sheath. 1. A self-powered in-core detector arrangement for measuring flux in a nuclear reactor core comprising: a first flux detecting material;', 'a first lead wire extending longitudinally from a first axial end of the first flux detecting material;', 'a first insulating material surrounding outer diameters of the first flux detecting material and the first lead wire; and', 'a first sheath surrounding the first insulating material, the first sheath including ...

COMPOSITE GAMMA-NEUTRON DETECTION SYSTEM

The present invention provides a gamma-neutron detector based on mixtures of thermal neutron absorbers that produce heavy-particle emission following thermal capture. The detector consists of one or more thin screens embedded in transparent hydrogenous light guides, which also serve as a neutron moderator. The emitted particles interact with the scintillator screen and produce a high light output, which is collected by the light guides into a photomultiplier tube and produces a signal from which the neutrons are counted. Simultaneous gamma-ray detection is provided by replacing the light guide material with a plastic scintillator. The plastic scintillator serves as the gamma-ray detector, moderator and light guide. The neutrons and gamma-ray events are separated employing Pulse-Shape Discrimination (PSD). The detector can be used in several scanning configurations including portal, drive-through, drive-by, handheld and backpack, etc. 1. A system for detection of neutrons and gamma rays , comprising:at least one light guide,a scintillator screen embedded into the light guide, wherein the scintillator screen comprises a thermal neutron absorber material, said material interacting with neutrons to emit heavy particles, and said heavy particles interacting with the scintillator screen to produce light,a first photodetector which receives the produced light through said light guide, and converts the light to a measurable signal,a plastic scintillator producing light on interaction with gamma-rays,a barrier placed along a length of said plastic scintillator and along a length of said scintillator screen to prevent cross-contamination between optical signals from the neutron and gamma detection materials,a second photodetector which collects the produced light from said plastic scintillator, and converts the light to a measurable signal, anda first counter and a second counter for counting pulses generated by the first photodetector and the second photodetector, ...

NEUTRON MONITOR DEVICE AND NEUTRON MEASUREMENT METHOD

Provided are a neutron monitor device and a neutron measurement method which make it easier to measure the intensity of the neutrons having the energy region of 10 KeV to several hundreds KeV. A neutron monitor device includes a first detector which includes a hemispherical first body formed of PE and having a radius of 31 mm, a first specimen containing GaN disposed at the center of the first body, a Cd layer provided on an outer surface of the first body, and a B layer provided inside the first body, and a second detector which includes a hemispherical second body formed of PE and having a radius of 27 mm, a second specimen containing GaN disposed at the center of the second body, a B layer provided on the outer surface of the second body, and a Cd layer provided inside the second body. 1. A neutron monitor device comprising:a first detector which includes a first body including a spherical portion of a predetermined radius formed of a hydrogen-containing material, a first specimen containing Ga disposed at the center of the spherical portion, a Cd layer provided on an outer surface of the spherical portion, and a B layer provided around the first specimen; anda second detector which includes a second body that is formed of a hydrogen-containing material and includes a spherical portion having a radius different from the radius of the spherical portion of the first detector, a second specimen containing Ga disposed at the center of the spherical portion, a B layer provided on the outer surface of the spherical portion, and a Cd layer provided around the second specimen.2. A neutron monitor device comprising:a first detector which includes a first body including a spherical portion of a predetermined radius formed of a hydrogen-containing material, a first specimen containing Ga disposed at the center of the spherical portion, and a B layer provided around the first specimen; anda second detector which includes a second body that is formed of a hydrogen-containing ...

Neutron Imager With Spaced Diamond Detector Arrays

A neutron detector system, with a detector having a pair of spaced diamond detector layers, sandwiched between outer silicon layers. In response to incident neutrons, the detector system measures pulse heights and response times, and from those measurements, calculates the carbon recoil energy and time of flight of scattered neutrons. This data is further used to calculate a “direction cone”, which represents the approximate angle of arrival of the incident neutron. These direction cones can be used to image neutron events.

INCORE NUCLEAR INSTRUMENTATION SYSTEM

In an incore nuclear instrumentation system which is equipped with a movable type neutron detector, an object of the invention is to control measurement errors due to the degradation of the system. The incore nuclear instrumentation system includes a neutron detector which is to be installed in a nuclear reactor stored in a containment vessel, and an instrumentation unit which has a current detector circuit and is to be installed on the outside of the containment vessel. An output signal of the neutron detector is inputted into the current detector circuit, and the instrumentation unit remembers a matrix which shows a relation among a reactor power of the nuclear reactor, a gain of the current detector circuit, and an output voltage Vn of the current detector circuit, and the calibration of the current detector circuit is performed with reference to the matrix. 1. An incore nuclear instrumentation system , comprisinga neutron detector which is to be installed in a nuclear reactor stored in a containment vessel, andan instrumentation unit which has a current detector circuit and is to be installed on the outside of the containment vessel,wherein an output signal of the neutron detector is inputted into the current detector circuit, andthe instrumentation unit remembers a matrix which shows a relation among a reactor power of the nuclear reactor, a gain of the current detector circuit, and an output voltage Vn of the current detector circuit, andthe calibration of the current detector circuit is performed with reference to the matrix.2. The incore nuclear instrumentation system according to claim 1 ,wherein the instrumentation unit performs, at a time when the calibration of the current detector circuit is performed,a first step for extracting an output voltage Vn corresponding to a present reactor power and a present gain from the matrix,a second step for judging whether the output voltage Vn extracted at the first step is smaller than a present output voltage Vout ...

NEUTRON MEASUREMENT APPARATUS AND NEUTRON MEASUREMENT METHOD

According to an embodiment, a neutron measurement apparatus has: a neutron detector; a preamplifier that amplifies an output signal of the neutron detector and outputs a neutron detection signal; a pulse counting unit that measures the neutron intensity by using pulse counting method by which the neutron detection signal is used to count the number of individual pulses; a Campbell measurement unit that measures the neutron intensity by using Campbell method by which a time average of squares of AC component of the neutron detection signal is calculated; a correction constant calculation unit that calculates a correction constant for correcting an output of the Campbell measurement unit by using an output of the pulse counting unit and an output of the Campbell measurement unit; and a correction value calculation unit that outputs, based on the output of the Campbell measurement unit, a corrected value by using the correction constant. 1. A neutron measurement apparatus to measure neutron intensity in a region where a nuclear reactor power is lower than the Power Range which is close to a rated reactor power , the apparatus comprising:a neutron detector to generate an output signal corresponding to an incoming neutron;a preamplifier to amplify an output signal of the neutron detector to output the amplified output signal of the neutron detector as a neutron detection signal;a pulse counting unit to measure the neutron intensity by using pulse counting method by which the neutron detection signal is used to count the number of individual pulses;a Campbell measurement unit to measure the neutron intensity by using Campbell method by which a time average of squares of. AC component of the neutron detection signals is calculated;a correction constant calculation unit to calculate a correction constant for correcting an output of the Campbell measurement unit by using an output of the pulse counting unit and an output of the Campbell measurement unit; anda correction ...

SYSTEMS, DEVICES, AND METHODS FOR BEAM POSITION MONITORING AND BEAM IMAGING

Embodiments of systems, devices, and methods relate to fast beam position monitoring for detecting beam misalignment in a beam line. In an example, a fast beam position monitor includes a plurality of electrodes extending into an interior of a component of a beam line. The fast beam position monitor is configured to detect a position of a beam passing through the component of the beam line based on beam halo current. Embodiments of systems, devices, and methods further relate to noninvasively monitoring parameters of beams advancing along a beam line. In examples, gas is puffed into a pumping chamber along a beam line. One or more beam parameters are measured from fluorescence resulting from collisions of energetic beam particulates of a beam advancing through the beam line. 1. A beam position monitor comprising a plurality of electrodes extending into an interior of a component of a beam line , wherein the beam position monitor is configured to detect a position of a beam passing through the component of the beam line based on halo current of the beam.2. The beam position monitor of claim 1 , further comprising a cooling device.3. The beam position monitor of claim 1 , wherein each electrode of the plurality of electrodes is associated with a current threshold.4. The beam position monitor of claim 1 , wherein at least one electrode of the plurality of electrodes is associated with a different current threshold than one or more other electrodes of the plurality of electrodes.5. The beam position monitor of claim 1 , wherein each electrode of the plurality of electrodes is associated with a plurality of current thresholds.6. The beam position monitor of claim 3 , wherein the beam position monitor is configured to transmit a signal to a control system when a measured current by one or more electrode of the plurality of electrodes exceeds its associated current threshold.7. The beam position monitor of claim 5 , wherein the beam position monitor is configured to ...

HIGH VOLTAGE SHIELDING TO ENABLE PASCHEN REGION OPERATION FOR NEUTRON DETECTION SYSTEMS

An electrical system for an atomic particle detection assembly includes an electrical component electrically connected to an atomic particle detection unit. The electrical system includes a dielectric insulating material surrounding the electrical component. The electrical system also includes a conductive shielding material surrounding the dielectric insulating material. The conductive shielding material and a conductive element are at substantially the same electric potential. 1. An electrical system for an atomic particle detection assembly , the electrical system including:an electrical component electrically connected to an atomic particle detection unit;a dielectric insulating material surrounding the electrical component; anda conductive shielding material surrounding the dielectric insulating material, wherein the conductive shielding material and a conductive element are at substantially the same electric potential.2. The electrical system of claim 1 , wherein the dielectric insulating material is in contact with the electrical component.3. The electrical system of claim 2 , wherein the dielectric insulating material includes a potting material.4. The electrical system of claim 2 , wherein the conductive shielding material surrounds and is in contact with the dielectric insulating material.5. The electrical system of claim 4 , wherein the conductive shielding material includes a metalized layer covering the dielectric insulating material.6. The electrical system of claim 1 , wherein the electrical component includes a conductive wire.7. The electrical system of claim 1 , wherein the electrical component is disposed within a chamber at an operating pressure that is less than about one atmosphere.8. An electrical system for an atomic particle detection assembly claim 1 , the electrical system including:an electrical component electrically connected to an atomic particle detection unit, the electrical component disposed within a chamber at an operating ...

OSCILLATION POWER RANGE MONITOR SYSTEM AND A METHOD OF OPERATING A NUCLEAR POWER PLANT

According to an embodiment, an oscillation power range monitor system has a plural of OPRM units. Each of the OPRM units has: the receiving cell-output set signals and averaging the cell-output set signals; a time average calculating unit calculating a time average cell value; a normalized cell value calculating unit calculating a normalized cell value; a trip determining unit outputting a reactor trip signal if amplitude or growth rate of oscillation or period of oscillation of the normalized cell value has exceeded a prescribed condition; a signal and prescribed value adjusting unit adjusting the relation between the normalized cell value and the specific value, thereby compensating for the deterioration in the neutron flux sensitivity of any LPRM detector in order to keep outputting the reactor trip signal. 1. An oscillation power range monitor system designed to monitor oscillation of power of a nuclear reactor and output a reactor trip signal to shut down the nuclear reactor automatically if the oscillation is found abnormal , the system comprising:a plurality of OPRM units, each of the OPRM units receiving and processing cell-output set signals coming from any selected LPRM detectors of LPRM strings arranged at the four corners of a cell of a lattice, the LPRM strings being arranged in a reactor core in the form of the lattice on the horizontal plane of the reactor core, each LPRM strings having a plurality of LPRM detectors configured to detect a neutron flux and a gamma-ray flux and having neutron flux sensitivity more decreasing than gamma-ray flux sensitivity over a period for measuring the neutron flux, wherein each of the OPRM units has:a cell average calculating unit receiving cell-output set signals and averaging the cell-output set signals, thereby calculating a cell average value;a time average calculating unit calculating a time average cell value that is temporal average of the value calculated by the cell average calculating unit in a prescribed ...

DETECTORS, SYSTEMS, AND METHODS FOR CONTINUOUSLY MONITORING NEUTRONS WITH ENHANCED SENSITIVITY

A neutron detector is disclosed herein. The neutron detector can include a housing defining a cavity, wherein the housing is configured to permit an amount of neutrons emitted from a core of a nuclear reactor to enter the cavity. The neutron detector can also include an amount of a neutron sensitive material dispositioned within the cavity, wherein the neutron sensitive material is configured to generate and emit gamma rays upon interacting with the amount of neutrons. The neutron detector can further include an amount of electron emissive material configured to generate and emit a current of electrons upon interacting with the emitted gamma rays, wherein the current of electrons is indicative of the amount of neutrons emitted from the core of the nuclear reactor. 1. A neutron detector comprising:a housing defining a cavity, wherein the housing is configured to permit an amount of neutrons emitted from a core of a nuclear reactor to enter the cavity;an amount of a neutron sensitive material dispositioned within the cavity, wherein the neutron sensitive material is configured to generate and emit gamma rays upon interacting with the amount of neutrons; andan amount of electron emissive material configured to generate and emit a current of electrons upon interacting with the emitted gamma rays, wherein the current of electrons is indicative of the amount of neutrons emitted from the core of the nuclear reactor.2. The neutron detector of claim 1 , wherein the electron emissive material is dispositioned between the housing and the neutron sensitive material.3. The neutron detector of claim 2 , further comprising an electrically insulating material is dispositioned between the electron emissive material and the housing.4. The neutron detector of claim 3 , wherein the current of electrons is configured to traverse through the cavity claim 3 , wherein the electrically insulating material is configured to allow the traversal of the current of electrons claim 3 , and wherein ...

SELF-POWERED IN-CORE DETECTOR ARRANGEMENT FOR MEASURING FLUX IN A NUCLEAR REACTOR CORE

A detector assembly for measuring flux in a nuclear reactor core includes a plurality of self-powered in-core detector arrangements each for measuring flux at a different one of a plurality of axial locations in the nuclear reactor core, and an assembly connector configured to be connected to a power plant connector. The assembly connector includes a plurality flux signal terminals each connected to one of self-powered in-core detector arrangements. At least one of the self-powered in-core detector arrangements comprises a set of at least two self-powered in-core detectors for measuring flux at a same one of the axial locations in the nuclear reactor core. Each of the at least two self-powered in-core detectors includes a sheath, a detector material section inside the sheath, an insulator between the sheath and the detector material, and a flux signal output line. The flux signal output lines of the at least two self-powered in-core detectors are joined together. 1. A detector assembly for measuring flux in a nuclear reactor core comprisinga plurality of self-powered in-core detector arrangements each for measuring flux at a different one of a plurality of axial locations in the nuclear reactor core; andan assembly connector configured to be connected to a power plant connector, the assembly connector comprising a plurality flux signal terminals each connected to one of self-powered in-core detector arrangements,at least one of the self-powered in-core detector arrangements comprising a set of at least two self-powered in-core detectors for measuring flux at a same one of the axial locations in the nuclear reactor core,each of the at least two self-powered in-core detectors including a sheath, a detector material section inside the sheath, an insulator between the sheath and the detector material, and a flux signal output line, the flux signal output lines of the at least two self-powered in-core detectors being joined together.2. The detector assembly as recited in ...

METHOD AND DEVICE FOR DETECTING ELEMENTARY PARTICLES

Provision is made in a method and a device for detecting elementary particles such as for example protons, ions, electrons, neutrons, photons or the like in a detector, wherein a charge pulse is generated in the detector when a particle passes through the detector and every charge pulse is subsequently converted into an electric signal and the signal is indicated and/or recorded in particular after amplification, for individual signals to be amplified in a first, fast amplifier and/or in each case a plurality of signals to be integrated in a second, slow amplifier, as a result of which it becomes possible for individual particles to be detected and in particular at increased signal or count rates for an integration thereof to be provided. 1. A method for detecting elementary particles such as for example protons , ions , electrons , neutrons , photons or the like in a detector , wherein a charge pulse is generated in the detector when a particle passes through the detector and every charge pulse is subsequently converted into an electric signal and the signal is indicated and/or recorded , in particular after amplification , wherein individual signals are amplified in a first , fast amplifier and/or a plurality of signals are each integrated in a second , slow amplifier , wherein discharging of a charge pulse or signal from the detector is performed on the low-voltage side.2. The method according to claim 1 , wherein claim 1 , as a function of the rate of the electric signals claim 1 , individual signals are amplified in the first claim 1 , fast amplifier and signals are integrated in the second claim 1 , slow amplifier at least upon exceeding of a threshold value of the rate of the signals.3. The method according to claim 1 , wherein the signals are separated as a function of the rate by a capacitor preceding at least a first amplifier for amplifying individual low-rate signals claim 1 , or a high-pass element claim 1 , and/or by an inductive element preceding at ...

Fast Neuron Spectroscopy with Tensioned Metastable Fluid Detectors

Systems and methods for neutron detection using tensioned metastable fluid detectors, using a single atom spectroscopy approach.

DETECTORS FOR USE WITH PARTICLE GENERATORS AND RELATED ASSEMBLIES, SYSTEMS AND METHODS

Neutron detectors for measuring a neutron yield of a neutron generator may include at least one particle counter disposed in a housing and at least one removable cartridge for receiving at least one collection medium. The at least one removable cartridge configured to be at least partially inserted into the housing to position the collection medium proximate the at least one particle counter. Detector assemblies for evaluating an output of a particle generator may include a housing and a plurality of cartridges that may be selectively received in the housing. Methods of detecting an output of a neutron source include inserting a collection medium into a cartridge, positioning the collection medium proximate a neutron source, and inserting the cartridge with the collection medium into a housing of a neutron yield detector. 1. A neutron detector for measuring a neutron yield of a neutron generator , the neutron detector comprising:a housing having an opening;at least one particle counter disposed in the housing; andat least one removable cartridge for receiving at least one collection medium, the at least one removable cartridge configured to be at least partially inserted into the housing through the opening to position the collection medium proximate the at least one particle counter, wherein the at least one removable cartridge is configured to be nondestructively removed from and inserted into the housing without requiring disassembly of the neutron detector.2. The neutron detector of claim 1 , wherein the at least one removable cartridge comprises at least one collection medium comprising a foil comprising a radioactive metallic material.3. The neutron detector of claim 2 , wherein the radioactive metallic material comprises radioactive isotypes of at least one of aluminum (Al) claim 2 , silicon (Si) claim 2 , or copper (Cu) and is configured to evaluate the neutron yield from a deuterium-tritium (DT) fusion reaction.4. The neutron detector of claim 2 , wherein ...

NUCLEAR FLOWMETER FOR MEASUREMENTS IN MULTIPHASE FLOWS

A nuclear flowmeter for measurements in multiphase flows consisting of up to three main phases that is connected in series in the output flow in a production line of an oil well, that includes a “U” shaped arrangement formed by an input branch and an output branch placed at both sides of the “U” shaped arrangement, where the input branch is connected to the production line of the oil well through an input pipe section () and the output branch is connected to the line of production of the oil well through an output pipe section () placed respectively at both ends of the “U” shaped arrangement; the input branch includes a pipe section with section reduction that forms a Venturi () while in the output branch includes a pipe section with possible section reduction () where the nuclear measurements are made, is provided. 1. A nuclear flowmeter for measurements in multiphase flows comprising up to three main phases that are connected in series to a production line of an oil well , where the pipe section of the output branch is placed between a storage , shield and transport compartment of an isotopic “fast” neutron source that includes said isotopic “fast” neutron source and neutron detectors included in the respective supports.2. The nuclear flowmeter for measurements in multiphase flows comprising up to three main phases that are connected in series in the outcome flow of a production line of an oil well claim 1 , according to claim 1 , having a “U” shaped arrangement formed by an input branch and an output branch placed at both sides of the “U” shaped arrangement claim 1 , where the input branch is connected to the production line of the oil well through an input pipe section and the output branch is connected to the line of production of the oil well through an output pipe section placed respectively at both ends of the “U” shaped arrangement; the input branch includes a pipe section with section reduction that forms a Venturi while in the output branch includes a ...

RADIATION SENSITIVE DEVICES AND SYSTEMS FOR DETECTION OF RADIOACTIVE MATERIALS AND RELATED METHODS

Radiation sensitive devices include a substrate comprising a radiation sensitive material and a plurality of resonance elements coupled to the substrate. Each resonance element is configured to resonate responsive to non-ionizing incident radiation. Systems for detecting radiation from a special nuclear material include a radiation sensitive device and a sensor located remotely from the radiation sensitive device and configured to measure an output signal from the radiation sensitive device. In such systems, the radiation sensitive device includes a radiation sensitive material and a plurality of resonance elements positioned on the radiation sensitive material. Methods for detecting a presence of a special nuclear material include positioning a radiation sensitive device in a location where special nuclear materials are to be detected and remotely interrogating the radiation sensitive device with a sensor. 1. A radiation sensitive device , comprising:a substrate comprising a radiation sensitive material exhibiting characteristics such that the radiation sensitive material at least partially ionizes when exposed to ionizing incident radiation; anda plurality of resonance elements comprising a conductive material coupled to the substrate, wherein each resonance element of the plurality of resonance elements is configured to resonate responsive to non-ionizing incident radiation to produce an output signal, wherein at least one characteristic of the output signal changes responsive to the radiation sensitive material at least partially ionizing when exposed to ionizing incident radiation.2. The radiation sensitive device of claim 1 , wherein each resonance element of the plurality of resonance elements has a shape selected from the group consisting of a simple dipole claim 1 , a bowtie dipole claim 1 , a spiral claim 1 , a square loop claim 1 , a square spiral claim 1 , a circular loop claim 1 , concentric loops claim 1 , an ellipse claim 1 , a rectangle claim 1 , a ...

NEUTRON MEASUREMENT APPARATUS AND NEUTRON MEASUREMENT METHOD

According to an embodiment, a neutron measurement apparatus has a neutron detector; a pre-amplifier; a first AC amplifier which extracts and amplifies an AC component; a bandwidth limiter which obtains a signal of a range of a predetermined frequency domain based on the output of the first AC amplifier; a neutron signal interval calculation unit which derives a neutron signal interval, that is a period of time during which a significant signal is being generated, from the AC component of the neutron detection signal; and a mean square value calculation unit which calculates a mean square value of outputs of the bandwidth limiter for a range corresponding to the neutron signal interval. 1. A neutron measurement apparatus comprising:a neutron detector to generate an output signal corresponding to an incoming neutron;a pre-amplifier to amplify the output signal of the neutron detector and to output a neutron detection signal;a first AC amplifier to extract and to amplify an AC component of the output of the pre-amplifier;a bandwidth limiter to obtain a signal of a range of a predetermined frequency domain based on the output of the first AC amplifier;a neutron signal interval calculation unit to derive a neutron signal interval, which is a period of time during which a significant signal is being generated, from the AC component of the neutron detection signal; anda mean square value calculation unit to calculate a mean square value of outputs of the bandwidth limiter for a range corresponding to the neutron signal interval.2. The neutron measurement apparatus according to claim 1 , wherein a second AC amplifier to extract and to amplify an AC component of the output of the pre-amplifier;', 'a wave height discriminator to classify wave heights into predetermined ranges based on an output of the second AC amplifier; and', 'a pulse length converter to derive the neutron signal interval based on an output of the wave height discriminator and to output a pulse signal ...

INDUCED NUCLEAR EXCITATION TRANSFER

An excitation transfer in a nuclear state is energetically induced. The excitation transfer may be induced by heating a structure to which a nuclear species is mechanically coupled. The heating may be applied as a triangular heat pulse. The heating may generate a stress effect in the structure. The stress effect may produce vibratory phonons. The excitation transfer may include up-conversion. The excitation transfer may include radioactive decay. The decay rate of a radioactive species may be increased to a rate higher than the natural half-life of the radioactive species. Energy may be harnessed from decay of the radioactive species. A decay product having industrial or medical use may be rapidly produced. The decay rate of the radioactive species may be lowered to reduce emissions for safe storage or transportation. 1. A method comprising:energetically inducing an excitation transfer in a nuclear state.2. The method of claim 1 , wherein energetically inducing an excitation transfer comprises energetically stimulating a sample using phonons.3. The method of claim 1 , wherein energetically inducing an excitation transfer comprises heating a structure to which a nuclear species is mechanically coupled.4. The method of claim 3 , wherein heating the structure comprises applying a heat pulse.5. The method of claim 3 , wherein heating the structure comprises generating a stress effect in the structure.6. The method of claim 5 , wherein the stress effect produces vibratory phonons.7. The method of claim 1 , wherein energetically inducing an excitation transfer comprises producing phonons using at least one of a laser claim 1 , an electric current claim 1 , and an ion beam.8. The method of claim 1 , wherein energetically inducing an excitation transfer comprises diffusing solutes to produce phonons in at least one of alloys claim 1 , solids claim 1 , solutions claim 1 , and condensed matter.9. The method of claim 1 , wherein the excitation transfer comprises up-conversion. ...

NUCLEAR RADIATION DOSIMETER USING STRESS INDUCED BIREFRINGENCE CHANGES IN FIBER OPTIC CABLES

The present invention relates to devices and methods for measuring neutron fluence at a pre-selected location which is positioned in a nuclear power plant. The devices and methods include passing neutrons through a fiber optic cable. The fiber optic cable has disposed therein a neutron sensitive material which is capable of absorbing the neutrons to produce a gas. The gas results in a build-up of pressure in the fiber optic cable which causes a change in the optical stress birefringence pattern. This change is measured and used to determine the amount of gas in the fiber optic cable, the number of neutrons absorbed by the neutron sensitive material and subsequently, the neutron fluence at the pre-selected location. 1. A device to measure neutron fluence in a pre-selected location in a nuclear power plant , the pre-selected location comprising a presence of neutrons , the device comprising:a fiber optic cable having a length and an outer surface which forms an cavity, the cavity extending through the length of the fiber optic cable;a neutron sensitive material substantially uniformly contained in the cavity, the neutron sensitive material effective to at least partially absorb the neutrons to produce a gas;an optical measurement tool for measuring a change in an optical stress birefringence pattern of the fiber optic cable, the change produced from a build-up of pressure as a result of the gas produced; anda means for determining an amount of the gas in the fiber optic cable and an amount of neutrons absorbed by the neutron sensitive material to determine total neutron exposure in the pre-selected location.2. The device of claim 1 , wherein the cavity has one or more cores formed therein.3. The device of claim 1 , wherein the one or more cores each substantially uniformly contains the neutron sensitive material.4. The device of claim 1 , wherein the gas is selected from the group consisting of hydrogen claim 1 , helium and mixtures thereof.5. The device of claim 1 , ...

SYSTEMS AND METHODS FOR SPENT FUEL POOL SUBCRITICALITY MEASUREMENT AND MONITORING

A system and method for measuring and monitoring axial flux to determine subcriticality in a spent fuel pool of a nuclear power plant. In certain embodiments of this invention, one or more neutron detectors are operable to generate signals resulting from neutron interactions in the spent fuel pool, a counting device counts the signals which are generated by the one or more neutron detectors, a connecting means electrically connects the one or more neutron detectors to the counting device, a signal analyzer is used to determine reactivity of the fuel assemblies in the spent fuel pool based on the counted signals, a power supply provides power for the neutron detectors, the counting device and the system analyzer, and a software code containing an axial flux curve index is used to correlate the counted signals to determine the subcriticality of the spent fuel pool. 1. A system for measuring and monitoring axial flux to determine subcriticality in a spent fuel pool of a nuclear power plant , which comprises:one or more neutron detectors operable to generate signals resulting from neutron interactions in the spent fuel pool;a counting device for counting said signals generated by the one or more neutron detectors;a connecting means to electrically connect the one or more neutron detectors to the counting device;a signal analyzer to determine reactivity of the fuel assemblies in the spent fuel pool based on counted signals;a power supply for the neutron detectors, the counting device and the signal analyzer; anda software code to correlate the counted signals to a predetermined axial flux curve index to determine the subcriticality of the spent fuel pool.2. The system of claim 1 , wherein the one or more neutron detector comprises at least one silicon carbide semiconductor diode.3. The system of claim 1 , wherein the nuclear power plant is a pressurized water reactor.4. The system of claim 1 , wherein the software code determines k-effective.5. The system of claim 4 , ...

NUCLEAR MATERIAL DETECTION DEVICE AND NUCLEAR MATERIAL DETECTION METHOD

A nuclear material within a container is to be detected. Included are: a neutron source for generating neutrons emitted toward the container; a detection section capable of detecting neutrons including primary neutrons emitted from the neutron source and secondary neutrons generated through a nuclear fission reaction of the nuclear material; and a processing section for performing a reactor noise analysis process based on data obtained through detecting of neutrons by the detection section. The neutron source generates neutrons in a pulsatile manner. The processing section performs the reactor noise analysis process based on data obtained by excluding, from time series data obtained through detecting of neutrons by the detection section, data of a time range including a generation time of the neutrons generated by the neutron source in the pulsatile manner. 1. A nuclear material detection device for detecting a nuclear material within an object , the nuclear material detection device comprising:a neutron source configured to generate neutrons used for irradiating the object;a detection section capable of detecting neutrons including primary neutrons emitted from the neutron source and secondary neutrons generated through a nuclear fission reaction of the nuclear material; anda processing section configured to perform a reactor noise analysis process based on data obtained through detecting of neutrons by the detection section, whereinthe neutron source generates neutrons in a pulsatile manner, andthe processing section performs the reactor noise analysis process based on data obtained by excluding data of a time range containing a generation time during which the neutron source generates the neutrons in the pulsatile manner, from time series data obtained through detecting of neutrons by the detection section.2. The nuclear material detection device according to claim 1 , wherein the processing section claim 1 , in addition to generating the time series data claim 1 ...

DISTANCE AND DIRECTION-SENSITIVE COSMOGENIC NEUTRON SENSORS

A cosmogenic neutron sensor includes a hydrogen-sensitive neutron detector orientable above a measurement surface. A neutron shield is positionable on the hydrogen-sensitive neutron detector. The neutron shield is positioned to interact with at least a portion of cosmogenic neutrons propagating in a direction of the hydrogen-sensitive neutron detector. 1. A cosmogenic neutron sensor , comprising:a hydrogen-sensitive neutron detector orientable above a measurement surface; anda neutron shield positionable on the thermal neutron detector, wherein the neutron shield is positioned to interact with at least a portion of cosmogenic neutrons propagating in a direction of the thermal neutron detector.2. The cosmogenic neutron sensor of claim 1 , wherein the neutron shield is positioned to interact with cosmogenic neutrons propagating from above the measurement surface.3. The cosmogenic neutron sensor of claim 1 , wherein the neutron shield is positioned to interact with cosmogenic neutrons propagating from a local area of the measurement surface below the hydrogen-sensitive neutron detector.4. The cosmogenic neutron sensor of claim 1 , wherein the neutron shield is positioned to interact with cosmogenic neutrons propagating from a portion of a wide area and a portion of a local area of the measurement surface below the hydrogen-sensitive neutron detector.5. The cosmogenic neutron sensor of claim 4 , wherein the neutron shield comprises a first neutron shield positionable on the hydrogen-sensitive neutron detector and a second neutron shield positioned below the hydrogen-sensitive neutron detector claim 4 , and wherein there is an air gap between the first neutron shield and the second neutron shield.6. The cosmogenic neutron sensor of claim 1 , wherein the neutron shield is positioned to interact with cosmogenic neutrons propagating from a wide area of the measurement surface below the hydrogen-sensitive neutron detector.7. The cosmogenic neutron sensor of claim 1 , further ...

MODERATED NEUTRON SENSOR

A moderated neutron detector includes a neutron detector having a first volume. A moderating enclosure is positioned around the neutron detector and encloses a second volume. The second volume is between 2 and 80 times larger than the first volume. A method for increased neutron detection includes the following steps: positioning a neutron detector within a moderating enclosure, wherein the neutron detector has a first volume, wherein the moderating enclosure encloses a second volume, and wherein the second volume is between 2 and 80 times larger than the first volume; increasing a quantity of neutrons impingent upon the neutron detector; and measuring the quantity of neutrons impinging upon the neutron detector. 1. A moderated neutron sensor , comprising:a neutron detector having a first volume; anda moderating enclosure positioned around the neutron detector and enclosing a second volume, wherein the second volume is between 2 and 80 times larger than the first volume.2. The moderated neutron sensor of claim 1 , wherein the neutron detector is centrally located within the moderating enclosure.3. The moderated neutron sensor of claim 1 , wherein the second volume is between 2 and 20 times larger than the first volume.4. The moderated neutron sensor of claim 3 , wherein the second volume is between 5 and 10 times larger than the first volume.5. The moderated neutron sensor of claim 1 , wherein a thickness of the moderating enclosure is between 0.5 and 2.0 inches.6. The moderated neutron sensor of claim 1 , wherein a difference between a depth of the neutron detector and a depth of the moderating enclosure is larger than a difference between a length of the neutron detector and a length of the moderating enclosure.7. A moderated neutron sensor claim 1 , comprising:a neutron detector having an exterior surface; anda moderating enclosure positioned around the neutron detector, wherein the moderating enclosure has an interior surface positioned a spaced distance away ...

ACCELERATING FISSILE MATERIAL DETECTION WITH A NEUTRON SOURCE

A neutron detector system for discriminating fissile material from non-fissile material wherein a digital data acquisition unit collects data at high rate, and in real-time processes large volumes of data directly to count neutrons from the unknown source and detecting excess grouped neutrons to identify fission in the unknown source. The system includes a Poisson neutron generator for in-beam interrogation of a possible fissile neutron source and a DC power supply that exhibits electrical ripple on the order of less than one part per million. Certain voltage multiplier circuits, such as Cockroft-Walton voltage multipliers, are used to enhance the effective of series resistor-inductor circuits components to reduce the ripple associated with traditional AC rectified, high voltage DC power supplies. 1. A system for characterizing a radiation source as fissile material or non-fissile material , comprising:a high voltage DC power supply comprising an AC filter circuit;a neutron generator coupled to the DC power supply and configured to irradiate the radiation source by inducing radiation in the radiation source;a detector configured to receive and count neutrons emitted from the radiation source; andan analyzer component coupled to the detector and configured to measure a number of neutrons simultaneously emitted from the radiation source during a number of measurement time periods to derive a multiplet count distribution, compute the mean count rate of the multiplet count distribution, compute the number of pairs of the multiplet count distribution, use the mean count rate to produce a Poisson distribution for the mean count rate, compute the expected number of pairs for the Poisson distribution, subtract the expected number of pairs for the Poisson distribution from the number of pairs in the measurement, and characterize the radiation source as fissile material if the number of pairs in the measurement exceeds the number of pairs for the Poisson distribution.2. The ...

ACCELERATING FISSILE MATERIAL DETECTION WITH A NEUTRON SOURCE

A neutron detector system for discriminating fissile material from non-fissile material wherein a digital data acquisition unit collects data at high rate, and in real-time processes large volumes of data directly to count neutrons from the unknown source and detecting excess grouped neutrons to identify fission in the unknown source. The system includes a Poisson neutron generator for in-beam interrogation of a possible fissile neutron source and a DC power supply that exhibits electrical ripple on the order of less than one part per million. Certain voltage multiplier circuits, such as Cockroft-Walton voltage multipliers, are used to enhance the effective of series resistor-inductor circuits components to reduce the ripple associated with traditional AC rectified, high voltage DC power supplies. 1. A method of characterizing a material as fissile or non-fissile , comprising:irradiating the material using an interrogation beam of neutrons generated from a pulsed electric source of neutrons; anddetecting, through a detector, neutrons emitted from the material while the interrogation beam is irradiating the material, wherein the detector is configured to distinguish between electric source neutrons in the interrogation beam and induced fission neutrons from the material.2. The method of further comprising:providing a DC power supply to power a system performing an analysis of the material; anda Poisson neutron source comprising the electric source for generating the interrogation beam, the Poisson neutron source configured to impose no electrical ripple to distort correlation of generated neutrons and to eliminate any problematic effect of electrical ripple on the DC power supply.3. The method of wherein the DC power supply comprises:two separate power supply stages configured such that their outputs are summed with a sinusoidal ripple added 180 degrees out of phase; anda Cockroft-Walton voltage multiplier configured to operate at a frequency that enhances an ...

Particle Detection System

A system to detect ionizing particles that includes an enclosure which holds a fluid in a tensioned metastable state. The interaction of a particle with the liquid creates a vapor pocket that can be seen and recorded, and also results in a shock wave that can be heard and recorded. The level of tension metastability in combination with agents, such as Be and B atoms, and surfactants that minimize evaporation losses is associated with a particular type of particle. 121-. (canceled)22. A system for detecting particles comprising a liquid in a first enclosure , wherein said liquid comprises at least one additive for broadening the energy range of detectable neutrons having energies in the range of from about 0.01 eV to about 10 MeV; said liquid comprising at least one neutron absorbing additive for the detection of photons; and a surface of said enclosure comprising a coating for the detection of alpha or photon particles , wherein said particles include at least one of: neutrons; protons , or alphas in the MeV range; wherein local regions of the liquid are in a metastable negative pressure state such that when said liquid is in the presence of said photons or particles a detectable vapor pocket forms and implodes to generate a detectable sonoluminescent light flash and a shock wave.23. The system of claim 22 , further comprising a secondary removable and rotatable enclosure surrounding the first enclosure claim 22 , the secondary enclosure having at least one open zero thickness window to permit directional passage of at least one of neutrons claim 22 , gamma rays claim 22 , and alpha particles thereby limiting said at least one neutrons claim 22 , gamma rays claim 22 , and alpha particles reaching said first enclosure to the direction of the source of the nuclear particle.24. The system of claim 22 , wherein the liquid is treated by compression of the enclosure and enclosed liquid; compression or filtration of the liquid ahead of introduction into the detector ...

Non-intrusive method to identify presence of nuclear materials using energetic prompt neutrons from photon-induced fission

Methods and systems for non-intrusively detecting the existence of fissile materials in a container via the measurement of energetic prompt neutrons are disclosed. The methods and systems use the unique nature of the prompt neutron energy spectrum from photo-fission arising from the emission of neutrons from almost fully accelerated fragments to unambiguously identify fissile material. The angular distribution of the prompt neutrons from photo-fission and the energy distribution correlated to neutron angle relative to the photon beam are used to distinguish odd-even from even-even nuclei undergoing photo-fission. The independence of the neutron yield curve (yield as a function of electron beam energy or photon energy) on neutron energy also is also used to distinguish photo-fission from other processes such as (γ, n). Different beam geometries are used to detect localized samples of fissile material and also fissile materials dispersed as small fragments or thin sheets over broad regions. These signals from photo-fission are unique and allow the detection of any material in the actinide region of the nuclear periodic table.

DEVICE FOR AND METHOD OF RECONSTRUCTING AXIAL MEASUREMENT VALUES IN NUCLEAR FUEL

In a device for and a method of reconstructing axial measurement values in a nuclear fuel, which is a device that calculates an axial reaction rate distribution by reconstructing a plurality of measurement values measured by a plurality of neutron flux detectors that are disposed at predetermined intervals in a fuel assembly along the axial direction of the fuel assembly, because a reconstruction parameter generator that generates a reconstruction parameter on the basis of core design data, or core analysis data, and a data adjustment factor; and an axial reaction rate distribution generator that calculates an axial reaction rate distribution on the basis of the measurement values that are measured by the neutron flux detectors and the reconstruction parameter that is generated by the reconstruction parameter generator are provided, an accurate axial measurement distribution in the nuclear fuel is obtained by reconstructing the measurement values. 15-. (canceled)6. A device for reconstructing axial measurement values in a nuclear fuel , the device calculating an axial measurement distribution by reconstructing a plurality of measurement values measured by a plurality of detectors that are disposed at predetermined intervals in the nuclear fuel along the axial direction of the nuclear fuel , the device comprising:a reconstruction parameter generator that generates a reconstruction parameter on the basis of core design data, or core analysis data, and a data adjustment factor; andan axial measurement distribution generator that calculates an axial measurement distribution in the nuclear fuel on the basis of the measurement values that are measured by the detectors and the reconstruction parameter that is generated by the reconstruction parameter generator,wherein the reconstruction parameter generator generates the reconstruction parameter on the basis of an inclination adjustment factor, an axial distribution adjustment factor, and an integral value adjustment factor ...

Neutron Detection and Collimation

A device includes a neutron-sensitive composition. The composition includes, in weight percent, a non-zero amount of aluminum oxide (e.g., approximately 1% to approximately 3.5% aluminum oxide), greater than 12% (e.g., approximately 12% to approximately 17%) boron oxide, greater than approximately 60% silicon oxide (e.g., approximately 62% to approximately 68% silicon oxide), and a non-zero amount of sodium oxide (e.g., approximately 10% to approximately 14% sodium oxide). The device is capable of interacting with neutrons to form an electron cascade. 1. A device , comprising: a non-zero amount of aluminum oxide,', 'approximately 12% to approximately 17% boron oxide,', 'greater than approximately 60% silicon oxide, and', 'a non-zero amount of sodium oxide,, 'a neutron-sensitive composition comprising, in weight percent,'}wherein the device is capable of interacting with neutrons to form an electron cascade.2. The device of claim 1 , wherein the boron oxide comprises substantially boron-10 enriched boron oxide.3. The device of claim 1 , wherein the composition further comprises a non-zero amount of calcium oxide less than approximately 4 weight percent.4. The device of claim 1 , wherein the composition further comprises a non-zero amount of magnesium oxide less than approximately 3 weight percent.5. The device of claim 1 , wherein the composition further comprises a non-zero amount of arsenic oxide or antimony oxide less than approximately 0.5 weight percent.6. The device of claim 1 , wherein the composition further comprises a non-zero amount of lithium oxide less than approximately 2 weight percent.7. The device of claim 1 , wherein the composition is substantially free of lead.8. The device of claim 1 , wherein the composition consists essentially of claim 1 , in weight percent claim 1 , approximately 1% to approximately 3.5% aluminum oxide claim 1 , approximately 12% to approximately 17% boron oxide claim 1 , approximately 62% to approximately 68% silicon oxide ...

Method for producing a neutron detector component comprising a boron carbide layer for use in a neutron detecting device

A method for producing a neutron detector component ( 1 ) comprising a neutron detecting boron carbide layer ( 2 ) comprising boron-10 arranged on a substantially neutron transparent substrate ( 3 ) is provided. The neutron detecting boron carbide layer ( 2 ) comprises boron-10 to a desired thickness (t), and wherein the boron-10 content of the neutron detecting boron carbide layer ( 2 ) is at least about 60 at. %.

Fast neutron spectroscopy with tensioned metastable fluid detectors

Systems and methods for neutron detection using tensioned metastable fluid detectors, using a single atom spectroscopy approach. 1. A portable system for detecting neutrons comprising, a detector liquid in a first enclosure having walls and a venturi valve system such that the detector liquid can pass therethrough during detector operation, the enclosure affixed to a spinning mechanism for introducing negative pressure in the detector liquid, wherein the spinning mechanism is capable of inducing a negative pressure in the detector liquid such that neutron detection can occur in the detector liquid at negative pressure and configured to detect neutron-caused vapor pocket corresponding to neutron counts, wherein the detection is based on [EV]=[RM]×[NE], where EV is a vector matrix of results of relative detection time for a range of Pvalues obtained experimentally by placing one or more detectors equidistance from an unknown neutron source, NE is a neutron energy vector, RM is a response matrix representing a probability matrix for detecting a neutron at a plurality of Pvalues, and Pis the tensioned negative pressure. The present application claims the benefit of the filing date of U.S. provisional application Ser. No. 62/398,572, filed 23 Sep. 2016, the contents of which are incorporated herein by reference.This invention was made with government support under DGE-0833366 and DGE-1333468 awarded by the National Science Foundation. The government has certain rights in the invention.The present application relates to systems and methods for neutron detection, and in particular to methods for neutron detection associated with tensioned metastable fluid detectors.This section introduces aspects that may help facilitate a better understanding of the disclosure. Accordingly, these statements are to be read in this light and are not to be understood as admissions about what is or is not prior art.The ability to perform neutron spectroscopy offers significant benefits ...

Particle event recordation

Presented herein are systems, methods, and nonvolatile computer-readable storage devices for informing a particle event processor of a particle detector of events arising within a sensor period. The systems, methods, and nonvolatile computer-readable storage devices involve the generation of a sensor data set detected by a particle event sensor and representing the events arising within the particle detector during the sensor period. The systems, methods, and nonvolatile computer-readable storage devices also involve the compression of the sensor data set with a waveform compression technique to generate a compressed sensor data set, and the transmission of the compressed sensor data set to the particle event processor.

Novel, Low-Cost, Light-Weight High Efficiency (H*10 Capable) Neutron Spectrometric Detector-Dosimeter

Systems and methods for neutron detection using tensioned metastable fluid detectors, using multi-atom spectroscopy approach. 1. A method for enabling neutron spectroscopy for ultra-low (˜10 micRem/h) to high (Rem/h) radiation field H*10 neutron dosimetry for separately or simultaneously covering the thermal-to-fast neutron energy spectrum , comprising: operating at least one non-doped Centrifugally Tensioned Metastable Fluid Detector (CTMFD) and at least one non-doped CTMFD operating in parallel.2. The method of claim 1 , further comprising developing a response matrix (RM) using a multi atom spectroscopy (MAS) approach comprising tertiary recoil ions contributing to cavitation detection events (CDEs).3. The method of claim 1 , further comprising developing sensitive volume (SV)-specific RMs and efficiency determination.4. The method of claim 1 , further comprising sensing fluids with minimal H content such as DFP claim 1 , PFO and PFPE for fast neutron spectroscopy claim 1 , including dopants in mixtures of TMFD fluids comprising trimethyl borate-methanol-DFP for enabling epithermal neutron and fast neutron spectroscopy.5. The method of claim 1 , further comprising a method for eliminating spurious CDEs via prior degassing claim 1 , mote control claim 1 , avoidance of gas ingress due to imbalanced accelerator claim 1 , and sealing for allowing long term false positive avoided operation.6. The method of claim 1 , wherein combination operation over various segmented Pneg ranges for deployment of various sized SV CTMFDs enables H*10 dosimetry and neutron spectrometry for continuous neutron spectra as from fission reactors claim 1 , spontaneous fission and/or (α claim 1 ,n) reactors claim 1 , and mixed field monoenergetic neutron beams from accelerator driven neutron generators.7. A portable system for detecting neutrons comprising: the spinning mechanism is capable of inducing a negative pressure in the detector liquid such that neutron detection can occur in the ...

Integrated Primary and Special Nuclear Material Alarm Resolution

The present specification discloses methods for inspecting an object. The method includes scanning an object in a two-step process. In the primary scan, a truck or cargo container (container) is completely scanned with a fan beam radiation, the transmitted radiation is measured with an array of detectors, and the transmission information and optionally the fission signatures are analyzed to determine the presence of high-density, high-Z and fissionable materials. If the container alarms in one or more areas, the areas are subjected to a secondary scan. This is done by precisely repositioning the container to the location of the suspect areas, adjusting the scanning system to focus on the suspect areas, performing a stationary irradiation of the areas, and analyzing the measured feature signatures to clear or confirm the presence of SNM. 1. An inspection system for inspecting an object using radiation comprising:a radiation source for generating and transmitting radiation;a collimator positioned in front of said radiation source wherein said collimator comprises two vertical structures defining a vertical slit through which said transmitted radiation is directed and a plurality of horizontally movable members positioned in front of said vertical slit, wherein said plurality of horizontally movable members each have a first configuration where they block more of the transmitted radiation from passing through the vertical slit and a second configuration where they block less of the transmitted radiation from passing through the vertical slit;a detector array for detecting a portion of transmitted radiation passing through said object; anda controller, wherein said controller is programmed to cause at least a portion of said horizontally movable members to move depending upon a scanning mode.2. The inspection system of wherein said scanning mode is a first stage scanning mode and wherein claim 1 , in response to the first stage scanning mode claim 1 , the controller ...

NON-INTRUSIVE METHOD TO IDENTIFY PRESENCE OF NUCLEAR MATERIALS USING ENERGETIC PROMPT NEUTRONS FROM PHOTON-INDUCED FISSION

Methods and systems for non-intrusively detecting the existence of fissile materials in a container via the measurement of energetic prompt neutrons are disclosed. The methods and systems use the unique nature of the prompt neutron energy spectrum from photo-fission arising from the emission of neutrons from almost fully accelerated fragments to unambiguously identify fissile material. The angular distribution of the prompt neutrons from photo-fission and the energy distribution correlated to neutron angle relative to the photon beam are used to distinguish odd-even from even-even nuclei undergoing photo-fission. The independence of the neutron yield curve (yield as a function of electron beam energy or photon energy) on neutron energy also is also used to distinguish photo-fission from other processes such as (γ, n). Different beam geometries are used to detect localized samples of fissile material and also fissile materials dispersed as small fragments or thin sheets over broad regions. These signals from photo-fission are unique and allow the detection of any material in the actinide region of the nuclear periodic table. 1. A method of determining a possible presence of a material comprising an actinide in a container , comprising:a) locating the container such that at least one neutron detector capable of distinguishing between photons and neutrons is positioned to view the said container at a first viewing angle relative to a photon beam;b) illuminating at least a portion of the said container with the photon beam comprising photons of energies no greater than a first predetermined cutoff photon energy;c) detecting in at least one of said at least one neutron detector some energetic prompt neutrons produced by fission reactions from an interaction of the said photon beam with at least a portion of the said container;d) for each of a plurality of said detected energetic prompt neutrons, determining an energy of the said detected neutron; ande) based upon the ...

SELF POWERED NUCLEAR DETECTOR

A self-powered neutron detector having an emitter with a slightly negative bias voltage that assures that an increase in the electrons that enter the insulator are counted and decreases or eliminates the gamma induced prompt signal. Variations in the size of the bias is used as a diagnostic tool to estimate the gamma induced prompt signal. 1. A self-powered neutron detector comprising:a neutron sensitive emitter element;an annular insulator substantially coaxially disposed around the emitter element;an outer electrically conductive sheath disposed around the annular insulator; anda negative bias voltage applied to the neutron sensitive emitter.2. The self-powered neutron detector of wherein the negative bias voltage is approximately between 1 and 30 volts.3. The self-powered neutron detector of wherein the negative bias voltage is approximately between 1 and 2 volts.4. The self-powered detector of including a coating of a material that enhances the photoemissivity of the emitter claim 1 , around at least a portion of the outside of the emitter.5. The self-powered detector of wherein the coating comprises selenium.6. The self-powered detector of including means for varying the negative bias voltage.7. A nuclear fuel assembly having an instrument thimble housing a self-powered neutron detector comprising:a neutron sensitive emitter element;an annular insulator substantially coaxially disposed around the emitter element;an outer electrically conductive sheath disposed around the annular insulator; anda negative bias voltage applied across the neutron sensitive emitter.8. The nuclear fuel assembly of wherein the negative bias voltage is approximately between 1 and 30 volts.9. The nuclear fuel assembly of wherein the negative bias voltage is approximately between 1 and 2 volts.10. The nuclear fuel assembly of including a coating of a material that enhances the photoemissivity of the emitter claim 7 , around at least a portion of the outside of the emitter.11. The nuclear ...

Combined Epithermal And Thermal Neutron Detector And Its Application To Well Logging Instruments

A combined thermal neutron and epithermal neutron radiation detector includes a plurality of neutron detecting elements arranged such that a first set of the detecting elements is disposed closer to a source of neutron flux scatted from a material or formation to be analyzed than a second set of detecting elements. The neutron detecting elements have a material therein susceptible to capture of thermal neutrons for detection. Signal outputs of the first set of are interconnected and signal outputs of the second set are separately interconnected to provide a signal output corresponding to each of thermal neutron flux and epithermal neutron flux entering the detector. 1. A combined thermal neutron and epithermal neutron radiation detector , comprising:a plurality of neutron detecting elements arranged such that a first set of the detecting elements are disposed closer to a source of neutron flux scattered from a material to be analyzed than a second set of neutron detecting elements, the neutron detecting elements having a material therein susceptible to capture of thermal neutrons; andwherein signal outputs of the first set of neutron detecting elements are interconnected and signal outputs of the second set of neutron detecting elements are separately interconnected to provide a signal output corresponding to each of thermal neutron flux and epithermal neutron flux entering the combination detector.2. The detector of wherein the neutron detecting elements comprise He filled tubes or straws.3. The detector of wherein the neutron detecting elements comprise boron coated straws.4. The detector of wherein the neutron detecting elements comprise compact proportional counters.5. The detector of wherein the neutron detecting elements comprise solid state devices embedded with neutron converting material.6. The detector of wherein the solid state material comprises lithium-6.7. The detector of further comprising a thermal neutron filter disposed between the first set and ...

TEMPERATURE MEASUREMENT SENSOR USING MATERIAL WITH A TEMPERATURE DEPENDENT NEUTRON CAPTURE CROSS SECTION

A temperature measurement sensor for use in a nuclear reactor is described and includes a first neutron detector member and a second neutron detector member wherein the first neutron detector member outputs a first current signal and the second neutron detector member outputs a second current signal. An electrical connection between the first and second signals produces a net current that is the difference in current between the first and second signals. The difference is proportional to changes in temperature. 1. A temperature measurement sensor for use in a nuclear reactor comprising:a first neutron detector member; anda second neutron detector member;each of the first and second neutron detector members being comprised of an inner electron emitter, a first layer of insulation surrounding the emitter, a charge collector surrounding the first layer of insulation, a negative charge output pin extending outwardly from the charge collector, and a positive charge output pin extending outwardly from the emitter;the first neutron detector member further comprising a second layer of insulation surrounding the first neutron detector charge collector, an electron absorbing layer surrounding the second layer of insulation and an outer shield for capturing neutrons surrounding the electron absorbing layer;wherein in use, the first neutron detector member outputs a first current signal and the second neutron detector member outputs a second current signal;an electrical connection between the first and second current signals capable of calculating the difference in current between the first and second signals, wherein the difference is proportional to changes in temperature.2. The sensor recited in wherein each electron emitter is made of a material that absorbs neutrons from radioactive decay and emits electrons.3. The sensor recited in wherein each electron emitter material is selected from the group consisting of rhodium and vanadium.4. The sensor recited in wherein each of ...

METHOD AND APPARATUS FOR DETECTION OF RADIOACTIVE ISOTOPES

A method and apparatus for detecting an isotope. Embodiments can detect radioactive isotopes. Embodiments can utilize a detector that incorporates at least two sub-detectors. Each sub-detector can receive energy from an isotope and create a signal corresponding to the received energy. Each sub-detector can incorporate a detector element, such as a detector element incorporating one or more diodes, a detector element incorporating a crystal, a detector element incorporating a solid-state device, or a detector element incorporating a scintillator. The sub-detectors can be configured such that for each isotope to be detected at least two of the sub-detectors produce different output signals, or readings. In an embodiment, each sub-detector is configured such that when there are at least two sub-detectors exposed to the isotope each of the corresponding readings from the sub-detectors is different from each of the other readings. 1. A detector , comprising:at least two sub-detectors, wherein the at least two sub-detectors are configured such that when the at least two sub-detectors are exposed to radiation from a radioactive isotope the at least two sub-detectors will output a corresponding at least two signals, wherein a ratio of a pair of the at least two signals identifies the radioactive isotope, wherein a first sub-detector of the at least two sub-detectors comprises a first filter having a first activation foil, wherein a second sub-detector of the at least two sub-detectors comprises a second filter having a second activation foil.2. The detector according to claim 1 , further comprising:a processor, wherein the processor receives two or more of the at least two signals and determines a ratio of a pair of the two or more of the at least two signals, wherein the processor uses the ratio of the pair of the two or more of the at least two signals to identify the radioactive isotope.3. The detector according to claim 1 , wherein each of the corresponding at least two ...

GAS-TIGHT PACKAGING OF DETECTORS

An atomic particle detection assembly includes one or more detectors that detect atomic particles. The detectors are positioned within a first chamber having a first operating pressure. The atomic particle detection assembly includes a junction apparatus supporting the detectors. The junction apparatus defines a second chamber having a second operating pressure that is different from the first operating pressure. Sensing electronics are attached to the detectors and the sensing electronics are housed within the second chamber of the junction apparatus. 1. An atomic particle detection assembly comprising:a detector configured to detect atomic particles, the detector being positioned within a first chamber having a first operating pressure;sensing electronics operatively attached to the detector; anda junction apparatus supporting the detector within the first chamber, the junction apparatus defining a second chamber having a second operating pressure that is different from the first operating pressure, the second chamber being sealed from the first chamber, and the junction apparatus including a housing within which the sensing electronics are housed.2. The atomic particle detection assembly of claim 1 , wherein the housing defines a portion of the second chamber such that the housing is maintained at the second operating pressure.3. The atomic particle detection assembly of claim 2 , wherein a second chamber channel extends from the housing towards the detector.4. The atomic particle detection assembly of claim 3 , wherein the second chamber channel is maintained at the second operating pressure and supports wires extending between the detector and the sensing electronics that are housed within the housing.5. The atomic particle detection assembly of claim 1 , wherein the second chamber of the junction apparatus defines a substantially enclosed volume that is not defined at an exterior of the junction apparatus.6. The atomic particle detection assembly of claim 1 , ...

ACTIVE CHARGED PARTICLE TOMOGRAPHY

An active radiation source portal monitoring system includes a particle accelerator to generate accelerated protons as a source of charged particles; a charged particles control unit to control the charged particles to enter into a volume to be scanned in a desired direction to interact with an object; a particle tracking unit to detect the charged particles exiting the volume after interacting with the object and generate signals indicative of information on the charged particles exiting the volume; and a signal processing unit communicatively coupled to the particle tracking unit. The signal processing unit can receive the generated signals and analyze scattering of the charged particles in one or more materials included in the object based on the received signals indicative of the information on the charged particles exiting the volume to obtain a tomographic profile or a spatial distribution of scattering centers within the object.

RADIATION DETECTION

An instrument for detecting radiation is provided, which comprises an inner core housing a neutron detector, and another core comprising a neutron-moderating material, the instrument further including at least one elongate thermal neutron guide located within the outer core and having an inner end that terminates proximal to the neutron detector. In use, the elongate thermal neutron guide channels thermal neutrons towards the neutron detector. Also provided is a method for using said instrument. 1. A method of detecting radiation , comprising contacting an instrument for detecting radiation with neutrons; i) an inner core comprising a neutron detector;', 'ii) an outer core comprising a neutron-moderating material, the outer core having an external surface; and', (a) the thermal neutron guide extends in a direction from the external surface of the outer core to the neutron detector and, in use, channels thermal neutrons towards the neutron detector, and', '(b) the inner end of the thermal neutron guide is proximal to the neutron detector., 'iii) at least one elongate thermal neutron guide having an inner end and an outer end, wherein the at least one elongate thermal neutron guide is located in the outer core, and wherein], 'wherein the instrument for detecting radiation, comprises2. The method of claim 1 , wherein the neutron-moderating material comprises a hydrogen-containing material.3. The method of claim 1 , wherein the outer core further comprises one or more different materials.4. The method of claim 3 , wherein the one or more different materials is a neutron-attenuating material.5. The method of claim 4 , wherein the neutron-attenuating material is boron or a boron-containing material.6. The method of claim 1 , wherein the at least one thermal neutron guide contacts the neutron detector.7. The method of claim 1 , wherein the at least one thermal neutron guide extends in a radial direction from the inner core towards the external surface of the outer core.8. ...

NEUTRON DETECTION USING POISSON DISTRIBUTION COMPARISON INDEPENDENT OF COUNT RATE BASED ON CORRELATION SIGNALS

Embodiments are directed to comparison-based methods of conditionally assessing the excess in correlation of an unknown neutron count measurement compared to the correlation present in a data defined as background, and to providing a technical definition of excess correlation intended to properly handle the measured excess correlation. The degree of correlation between an unknown source and background can be used to prevent masking of neutron count data for the source by background radiation. 1. A computer-implemented method of analyzing radiation of a target source relative to background , comprising:measuring, for a first number of cycles, neutrons detected by a detector not placed in proximity to the target source to derive a background multiplicity count distribution of different multiplet sizes for a defined observation time;normalizing the background multiplicity count distribution to derive normalized background multiplets by dividing a number neutron detections for each multiplet size by the first number of cycles;deriving, in a processor system coupled to the detector, a set of background count distributions based on the normalized background multiplets to define a normalized correlation indicator;measuring, for a second number of cycles, neutrons detected by the detector placed in proximity to the target source to derive a source multiplicity count distribution of different multiplet sizes for the defined observation time;normalizing the source multiplicity count distribution to derive normalized source multiplets by dividing a number of neutron detections for each multiplet size by the second number of cycles; anddetermining if each normalized source multiplet exceeds each respective normalized background multiplet by a threshold defined by the normalized correlation indicator.2. The method of wherein the normalized correlation indicator is derived by dividing a first normalized background multiplet value by a second normalized background multiplet value. ...

Method for producing neutron converters

The present invention relates to a method for producing a neutron converter from boron carbide or a boron film on a neutron transparent metal substrate. The neutron transparent metal substrate is polished in a first step by fine grinding and coated in a further step by means of sputtering with boron carbide or a boron film. An adhesion promoting layer is optionally applied between the metal substrate and below the boron or boron carbide layer. The coatings obtained have a high homogeneity in layer thickness, chemical composition and isotope ratio as well as a low level of impurities such as oxygen or nitrogen.

METHODS AND SYSTEMS FOR DETECTING EPITHERMAL AND THERMAL NEUTRONS

A system includes a tool for measuring properties of a formation. The tool includes a tool body, a neutron source to emit neutrons disposed within the tool body, a neutron detector disposed within the tool body spaced apart from the neutron source, and a neutron shield arranged in operational relationship to the neutron detector, the neutron shield defines an exterior surface and an interior volume, the neutron shield to prevent neutrons having an energy below a first predetermined threshold from traveling from the exterior surface to the interior volume. The neutron shield is movably coupled to the tool body, wherein the neutron shield defines a non-occluded position relative to the neutron detector such that the neutron detector is at least partially outside the interior volume, and the neutron shield defines an occluded position relative to the neutron detector such that the neutron detector is disposed within the interior volume. 1. A system comprising: a tool body;', 'a neutron source disposed within the tool body, the neutron source to emit neutrons;', 'a neutron detector disposed within the tool body at a spaced apart location from the neutron source;', 'a first neutron shield arranged in operational relationship to the neutron detector, the first neutron shield defines an exterior surface and an interior volume, the first neutron shield to prevent neutrons having an energy below a first predetermined threshold from traveling from the exterior surface to the interior volume;', 'the first neutron shield movably coupled to the tool body, wherein the first neutron shield defines a non-occluded position relative to the neutron detector such that the neutron detector is at least partially outside the interior volume, and the first neutron shield defines an occluded position relative to the first neutron detector such that the first neutron detector is disposed within the interior volume., 'a tool for measuring properties of an earth formation, the tool comprising2 ...

Neutron Monitoring System

A neutron monitoring system for monitoring a state of a fuel used in a nuclear power plant includes the following: neutron detector; a structural material to which the neutron detector is mounted; a water detection sensor mounted at a position corresponding to the same height as is the neutron detector, the water detection sensor including a thermocouple and a heating element; an amplification circuit configured to amplify a neutron monitoring signal sent from the neutron detector; a temperature measuring circuit connected to a thermocouple of the water detection sensor via strands; a heater power supply connected to a heating element of the water detection sensor via heater lead wires; a water existence determining control section configured to determine whether the water detection sensor is underwater; and a correction circuit configured to correct an output signal value of the amplification circuit in accordance with a determination signal from the water existence determining control section. 1. A neutron monitoring system for monitoring a state of a fuel used in a nuclear power plant , the system comprising:a neutron detector;a structural material to which the neutron detector is mounted;a water detection sensor mounted at a position corresponding to the same height as is the neutron detector, the water detection sensor including a thermocouple and a heating element;an amplification circuit configured to amplify a neutron monitoring signal sent from the neutron detector;a temperature measuring circuit connected to a thermocouple of the water detection sensor via strands;a heater power supply connected to a heating element of the water detection sensor via heater lead wires;a water existence determining control section configured to determine whether the water detection sensor is underwater; anda correction circuit configured to correct an output signal value of the amplification circuit in accordance with a determination signal from the water existence ...

INCORE NEUTRON INSTRUMENTATION SYSTEM

Non-contact sensors are used as a pull-out limit switch and a safety limit switch, so that contact between a drive cable and a thimble tube and both limit switches is avoided and abrasion of both limit switches is eliminated. In addition, erroneous detection due to vibration of the thimble tube is prevented by eliminating contact between the thimble tube and both limit switches, whereby accuracy of passing of a detector is enhanced. 15.-. (canceled)6. An incore neutron instrumentation system comprising:a detector measuring a neutron flux within a nuclear reactor;a drive cable connected to the detector and moving the detector to a measurement position within the nuclear reactor;a thimble tube which is a hollow passage in which the detector and the drive cable move;a drive unit driving the drive cable for moving the detector;a control panel for controlling the drive unit;a pull-out limit switch disposed in non-contact with the drive cable and the thimble tube and outputting a signal for determining presence/absence of passing of the detector, for pulling out the detector from the measurement position within the nuclear reactor and stopping the detector at a predetermined stop position;a safety limit switch disposed in non-contact with the drive cable and the thimble tube and outputting a signal for determining presence/absence of passing of the detector and turning off power of the drive unit, for turning off the power of the drive unit and stopping movement of the detector; anda signal transmission unit transmitting output signals from the pull-out limit switch and the safety limit switch, to the control panel, whereinthe detector is moved from an inside of the nuclear reactor to an outside of the nuclear reactor or from the outside of the nuclear reactor to the inside of the nuclear reactor, and a neutron flux generated within the nuclear reactor is measured.7. The incore neutron instrumentation system according to claim 6 , wherein the pull-out limit switch and the ...

Staggered Detector Array for Locating Radioactive Sources

A large-area directional radiation detection system may include a large number of slab-shaped detectors stacked side-by-side and alternately displaced frontward and rearward, thereby providing a longitudinally-staggered array of protruding and recessed detectors. The protruding detectors collimate or restrict the lateral field of view of the recessed detectors, thereby enabling the angular position and distance of a source to be determined. The high detection efficiency and large solid angle of the staggered detector array enable rapid detection of even well-shielded threat sources at substantial distances, while simultaneously determining the positions of any sources detected. This detector array will be essential for guarding against clandestine delivery of nuclear materials in the coming century. 2. The detector array of claim 1 , wherein the detector array includes no shields or passive collimators.3. (canceled)4. The detector array of claim 1 , wherein the processor is configured to receive signals from the detectors and to determine claim 1 , based at least in part on the signals claim 1 , at least one of:a front-versus-back position of the source;a distance of the source from the detector array;an angle of the source relative to the detector array; anda lateral position of the source relative to the detector array.5. The detector array of claim 1 , wherein the processor is configured to determine a frontward detection peak comprising a subset of the frontward detectors that have enhanced detection claim 1 , and to determine a rearward detection peak comprising a subset of the rearward detectors that have enhanced detection.6. The detector array of claim 5 , further comprising non-transient computer-readable media containing instructions that claim 5 , when executed claim 5 , cause the processor to determine the width of the frontward and the width of the rearward detection peak by at least one of:calculating a full-width-at-half-maximum for each detection ...

DOSIMETER WITH RFID TAG

Described is device comprising dosimeter for measuring one or more doses of radiation; and an RFID tag comprising an antenna for communicating with an RFID tag reader and non-volatile memory for storing data therein. 116-. (canceled)17. A device comprising:a dosimeter for measuring one or more doses of radiation; and an antenna for communicating with an RFID tag reader, and', 'a non-volatile memory for storing data,, 'a radio frequency identification (RFID) tag comprisingwherein the dosimeter comprises one or more optically stimulated luminescence (OSL) sensors,wherein the dosimeter is configured to have adjusted readout radiation dose data for the dosimeter written to and stored on the non-volatile memory by a current dosimeter reader that reads current radiation dose data from the one or more OSL sensors,wherein the dosimeter is configured to store historical data,wherein the dosimeter is configured to have the historical data read by the current dosimeter reader,wherein the adjusted radiation dose data comprises current readout radiation dose data that has been adjusted based on the historical data read by the current dosimeter reader,wherein the historical data comprises radiation dose data for the dosimeter that has been readout by one or more prior dosimeter readers and written to the non-volatile memory by one or more of the one or more prior dosimeter readers.18. The device of claim 17 , wherein the current dosimeter reader is one of the one or more prior dosimeter readers.19. The device of claim 17 , wherein the historical data comprises calibration data for one or more of the one or more of the OSL sensors.20. The device of claim 17 , wherein the dosimeter is part of a badge that may be worn by an individual.21. The device of claim 17 , wherein the historical data comprises identification information for a model type of the dosimeter.22. The device of claim 17 , wherein the historical data comprises a dosimeter serial number for the dosimeter.23. The ...

Radiation imaging apparatus, method for controlling the same, storage medium, and radiation imaging system

A radiation imaging apparatus that communicates via wired communication with an irradiation control apparatus includes a radiation detection unit that detects incident radiation and obtains a moving image related to the radiation, and an imaging control unit that, in a first case where the wired communication is disconnected in a moving image capturing state in which the moving image is captured, performs control to set the moving image capturing state, and in a second case where the wired communication is disconnected not in the moving image capturing state and moving image capturing is set as next imaging, performs control to set a moving image standby state that is a standby state for the moving image capturing.

NEUTRON ASSAY

Disclosed are systems and methods for detecting fissile material. The systems and methods include devices and operations for measuring background neutron detection events using a plurality of fast neutron detectors arranged around a stimulation neutron source, measuring sample neutron detection events using the plurality of fast neutron detectors arranged around a small volume of sample material, measuring stimulated neutron detection events using the plurality of fast neutron detectors when the sample material is irradiated by the stimulation neutron source, (which in various implementations, includes determining a number of single neutron detection events), and determining a presence of fissile material in the sample material based upon the background neutron detection events, sample neutron detection events and the stimulated neutron detection events. 1. A method of detecting fissile material , comprising:measuring background neutron detection events using a plurality of fast neutron detectors arranged around a stimulation neutron source;measuring sample neutron detection events using the plurality of fast neutron detectors arranged around a small volume of sample material;measuring stimulated neutron detection events using the plurality of fast neutron detectors when said sample material is irradiated by the stimulation neutron source, wherein the measuring comprises determining a number of single neutron detection events; anddetermining a presence of fissile material in the sample material based upon the background neutron detection events, sample neutron detection events and the stimulated neutron detection events.2. The method of claim 1 , wherein the single neutron detection events are within a predetermined window of time.3. The method of claim 2 , wherein the measuring comprises determining a number of two or more neutron detection events within the predetermined window of time.4. The method of claim 1 , wherein the measuring comprises determining the ...

ADVANCED FISSILE NEUTRON DETECTION SYSTEM AND METHOD

A fissile neutron detection system includes an ionizing thermal neutron detector arrangement including an inner peripheral shape that at least substantially surrounds a moderator region for detecting thermal neutrons that exit the moderator region but is at least generally transparent to the incident fissile neutrons. A moderator is disposed within the moderator region having lateral extents such that any given dimension that bisects the lateral extents includes a length that is greater than any thickness of the moderator arrangement transverse to the lateral extents. The moderator can include major widthwise and major lengthwise lateral extents such that any given dimension across the lengthwise and widthwise lateral extents includes a length that is greater than any thickness of the moderator arrangement transverse to the lateral extents. 1. A fissile neutron detection system for detecting incident fissile neutrons , said fissile neutron detection system , comprising:an ionizing thermal neutron detector arrangement including an inner peripheral shape that at least substantially surrounds a moderator region for detecting thermal neutrons that exit the moderator region but is at least generally transparent to the incident fissile neutrons; anda moderator arrangement disposed within the moderator region for converting the incident fissile neutrons in the moderator region to thermal neutrons which exit the moderator region to then enter the thermal neutron detector arrangement for detection of at least some of the thermal neutrons to produce an electrical current as a detector output with the moderator arrangement having an outer peripheral shape that is at least generally complementary to said inner peripheral shape and the moderator arrangement includes lateral extents such that any given dimension that bisects the lateral extents includes a length that is greater than any thickness of the moderator arrangement transverse to the lateral extents.2. The fissile ...

Neutron Detection

A method for detecting a neutron includes providing a first voltage to an input electrode of a microchannel plate, providing a second voltage to an output electrode of the microchannel plate, the second voltage being more positive than the first voltage, measuring a signal on the output electrode, and detecting a neutron based on a comparison of the signal at the output electrode with a baseline value. 1. A method for detecting a neutron , the method comprising:providing a first voltage to an input electrode of a microchannel plate;providing a second voltage to an output electrode of the microchannel plate, the second voltage being more positive than the first voltage;measuring a first signal on the input electrode;measuring a second signal on the output electrode; anddetecting a neutron based on a comparison of the first and second signals.2. The method of in which detecting a neutron comprises determining that a neutron has been detected when the polarity of the second signal is opposite to that of the first signal for a period of time.3. The method of in which detecting a neutron comprises determining that a neutron has been detected when the amplitude of the second signal is also above a predetermined threshold.4. The method of in which detecting a neutron comprises determining that a neutron has been detected when the polarity of the first and second signals are the same for a first period of time and opposite for a second period of time.5. The method of claim 1 , comprising detecting an avalanche of secondary electrons reaching an anode of the microchannel plate.6. The method of in which detecting a neutron comprises determining that a neutron has been detected when claim 4 , for a period of time after the avalanche of secondary electrons have been detected claim 4 , the polarity of the second signal is opposite to that of the first signal.7. The method of claim 1 , comprising integrating the first signal over a period of time to generate a first integral ...