Method for detecting high-energy radiation using low voltage optimized ion chamber

A method for measuring high-energy radiation flux, comprising applying a low voltage to electrodes in an ion chamber filled with a fluid capable of forming ions through the interaction of the fluid with high energy radiation; measuring an ion current signal related to an ion current induced by the low voltage; determining a leakage current; determining a gain; determining a magnitude of the high-energy radiation flux based on the ion current signal, gain, and leakage current; and outputting the result of the magnitude of the high-energy radiation flux.

Systems, methods, and apparatus for anode and cathode electrical separation in detectors

Certain embodiments of the invention may include systems, methods, and apparatus for providing anode and cathode electrical separation in detectors. According to an example embodiment of the invention, a method is presented for providing a neutron detector tube. The method may include applying a conductive layer to at least a portion of an inner surface of a non-conductive cathode tube associated with a neutron detector; applying a neutron sensitive cathode coating to at least a portion of the conductive layer; sealing a first portion of the neutron detector tube with a cathode cap; and sealing a second portion of the neutron detection tube with an anode cap.

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.

He-3 tube array alignment mount

An arrangement for detecting energy particle impingement includes a support frame and a multi-tube detector pack. Each pack includes multiple detector tubes. Each tube contains at least one sensitive material. Each tube is elongate along a respective axis. The tubes extend parallel with the respective axes being co-planar. Each pack includes mounting tabs located at each axial end. The tabs provide support for the tubes within the pack. At least one of the tabs has at least one securing portion and at least one adjusting portion. Each pack includes at least one operable securing member extending from the respective securing portion to the frame. Operation of the securing member secures the pack to the support frame. Each pack includes at least one operable adjusting member extending from the respective adjusting portion to the frame. Operation of the adjusting member changes an orientation of the pack.

Methods and Systems for Time-of-Flight Neutron Interrogation for Material Discrimination

The present invention provides a Time-of-Flight based neutron inspection system. The system employs a collimated beam of fast neutrons for targeted interrogation of suspect areas in cargo. Elemental composition is determined as a function of depth. Analysis is then used to determine the presence of contraband. The system may be used for secondary inspection for material discrimination to reduce false alarm rate and high cost and time associated with manual unpacking 1. A system for inspection of a suspect area in an object , comprising:{'sup': '9', 'a nano-second pulsed deuteron generator, for generating at least 10neutrons/second, said generator comprising an ion source to produce a beam of deuterium ions, and an ion filter, chopper and buncher for shaping the beam of deuterium ions into a narrow pulse width;'}a tritium target, which produces pulsed neutrons on being impinged by a pulsed beam of deuterium ions;a movable collimator to aim the pulsed neutrons at the suspect area;gamma-ray detectors to detect gamma rays produced after the interaction of pulsed neutrons with the suspect area; anda processing unit that analyzes Time-of-Flight (ToF) data from the detectors to determine materials in the suspect area.2. The system of wherein the processing unit uses ToF data to map signals from gamma-ray detectors into the elements of suspect area as a function of depth.3. The system of claim 1 , wherein the current of deuteron beam impinging on the tritium target is in the range of 100 μA.4. The system of claim 1 , wherein the accelerating voltage is in the 100 to 300 kV range.5. The system of claim 1 , wherein the ion source is a positive ion source.6. The system of claim 1 , wherein the tritium target comprises multiple targets.7. The system of claim 1 , wherein the tritium target comprises a rotating target.8. The system of claim 1 , wherein the neutron generator is shielded to reduce dose outside the collimated beam and reduce gamma-ray background and wherein said ...

Advanced thermal neutron detectors and associated methods

A narrow thermal neutron detector includes a slidably receivable ionization thermal neutron detector module within an overall housing body. An active sheet layer of the ionization thermal neutron detector module can be tensioned across its width. The ionization thermal neutron detector module can include module upper major surface extents and module lower surface extents such that, when installed within the housing body, the module upper major surface extents are in a first spaced apart confronting relationship with housing upper major surface extents to define a first clearance and module lower major surface extents are in a second spaced apart confronting relationship with housing lower major surface extents to define a second clearance to accommodate housing flexing due to ambient pressure change. The housing body can be formed with a single opening for receiving the ionization thermal neutron detection module or with opposing first and second opposing end openings.

SLOW NEUTRON DETECTION DEVICE

A slow neutron detection device is disclosed, comprising: a first slow neutron converter and a second slow neutron converter, and a readout electrode wire set and cathode wire sets arranged between the first slow neutron converter and the second slow neutron converter. By arranging a readout circuit between the two slow neutron converters, an electron drift distance is reduced by half without changing a dimension of the detection device, and an average over-threshold probability of a signal is increased. 1. A slow neutron detection device , comprising:a first slow neutron converter and a second slow neutron converter configured to react with incident neutrons and generate electrons; andan electron multiplication and readout apparatus arranged between the first slow neutron converter and the second slow neutron converter and configured to multiple and read out the electrons.2. The slow neutron detection device according to claim 1 , wherein the electron multiplication and readout apparatus comprises:a first cathode wire set including a plurality of electrode wires disposed in parallel, the first cathode wire set being arranged between the first slow neutron converter and the second slow neutron converter and near one end of the first slow neutron converter;a second cathode wire set including a plurality of electrode wires disposed in parallel, the second cathode wire set being arranged between the first slow neutron converter and the second slow neutron converter and near one end of the second slow neutron converter; anda readout electrode wire set including a plurality of electrode wires disposed in parallel and working as an anode, the readout electrode wire set being arranged between the first cathode wire set and the second cathode wire set, the plurality of electrode wires of the readout electrode wire set being substantially perpendicular to a direction along which the plurality of electrode wires of the first cathode wire set extend and a direction along which ...

Advanced thermal neutron detectors and methods

A narrow thermal neutron detector includes a slidably receivable ionization thermal neutron detector module within an overall housing body. An active sheet layer of the ionization thermal neutron detector module can be tensioned across its width. The ionization thermal neutron detector module can include module upper major surface extents and module lower surface extents such that, when installed within the housing body, the module upper major surface extents are in a first spaced apart confronting relationship with housing upper major surface extents to define a first clearance and module lower major surface extents are in a second spaced apart confronting relationship with housing lower major surface extents to define a second clearance to accommodate housing flexing due to ambient pressure change. The housing body can be formed with a single opening for receiving the ionization thermal neutron detection module or with opposing first and second opposing end openings.

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 ...

FISSILE NEUTRON DETECTOR

A fissile neutron detection system includes a neutron moderator and a neutron detector disposed proximate such that a majority of the surface area of the neutron moderator is disposed proximate the neutron detector. Fissile neutrons impinge upon and enter the neutron moderator where the energy level of the fissile neutron is reduced to that of a thermal neutron. The thermal neutron may exit the moderator in any direction. Maximizing the surface area of the neutron moderator that is proximate the neutron detector beneficially improves the reliability and accuracy of the fissile neutron detection system by increasing the percentage of thermal neutrons that exit the neutron moderator and enter the neutron detector. 1. A fissile neutron detection system for detecting incident fissile neutrons , said fissile neutron detection system , comprising:an ionizing thermal neutron detector arrangement defining an inner peripheral shape that at least substantially surrounds a moderator region for detecting thermal neutrons that exit the moderator region but the incident fissile neutrons at least generally pass through the ionizing thermal neutron arrangement; 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 signal 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 system of wherein the thickness of the moderator arrangement is in a range from 1 cm ...

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.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 has a length of about 0.31 times the straw diameter or less.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 2 , wherein the septa are about 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 detector system of claim 7 , wherein the length of each septum is between about 50% and 100% of an arch length between each septum.10. The straw detector system of claim 7 , wherein the length of each septum is greater than or equal to 0.95 times the length of an arch between each septum.11. The straw detector system of claim 2 , wherein the ...

ADVANCED THERMAL NEUTRON DETECTORS AND ASSOCIATED METHODS

A narrow thermal neutron detector includes a slidably receivable ionization thermal neutron detector module within an overall housing body. An active sheet layer of the ionization thermal neutron detector module can be tensioned across its width. The ionization thermal neutron detector module can include module upper major surface extents and module lower surface extents such that, when installed within the housing body, the module upper major surface extents are in a first spaced apart confronting relationship with housing upper major surface extents to define a first clearance and module lower major surface extents are in a second spaced apart confronting relationship with housing lower major surface extents to define a second clearance to accommodate housing flexing due to ambient pressure change. The housing body can be formed with a single opening for receiving the ionization thermal neutron detection module or with opposing first and second opposing end openings. 1. A thermal neutron detector for detecting thermal neutrons , said thermal neutron detector comprising:a housing defining a housing cavity;an ionization detector module having a peripheral outline that is complementary to the housing within the housing cavity, the ionization detector module having a length, a width and a height with the height being less than each of the length and the width, the ionization detector module including a framework to which an active sheet layer is fixedly attached, the framework including an opposing pair of lengthwise side margins extending between another pair of widthwise side margins to define a rectangular shape supporting the active sheet layer to span at least a majority of said length and width and a support to engage at least one of the lengthwise side margins of the framework to apply a tension force to the framework between the lengthwise side margins such that the active sheet layer is under tension across the width of the ionization detector module;an ...

Miniaturized fast neutron spectrometer

An isotropic neutron detector includes a spherical secondary particle radiator component and a plurality of stacked semiconductor detectors, A first semiconductor detector is coupled to at least a portion of the spherical secondary particle radiator component, forming a portion of a first concentric shell thereover. A second semiconductor detector coupled to at least a portion of the first semiconductor detector, forming a portion of a second concentric shell thereover.

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 , ...

Neutron Detection

A neutron detector includes a microchannel plate having a structure that defines a plurality of microchannels, and layers of materials disposed on walls of the microchannels. The layers include a layer of neutron sensitive material, a layer of semiconducting material, and a layer of electron emissive material. For example, the layer of neutron sensitive material can include boron-10, lithium-6, or gadolinium. 1. An apparatus comprising: a plurality of microfibers that define interstices between the microfibers;', 'layers of materials disposed on surfaces of the microfibers, the layers including a layer of neutron sensitive material, a layer of semiconducting material, and a layer of electron emissive material;', 'an input electrode; and', 'an output electrode, in which the microfibers are disposed between the input and output electrodes., 'a microfiber plate comprising2. The apparatus of in which the layer of neutron sensitive material comprises at least 50 mol % of neutron sensitive material.3. The apparatus of in which the layer of neutron sensitive material comprises at least one of boron-10 claim 1 , lithium-6 claim 1 , or gadolinium.4. The apparatus of in which the layer of neutron sensitive material comprises a compound that comprises at least one of boron-10 claim 1 , lithium-6 claim 1 , or gadolinium claim 1 , and the compound comprises at least one of boron-10 oxide claim 1 , boron-10 nitride claim 1 , lithium-6 oxide claim 1 , or gadolinium oxide.5. The apparatus of in which the layer of neutron sensitive material has a thickness in a range from 0.5 to 5 microns.6. The apparatus of in which the layer of semiconducting material has a thickness in a range from 50 to 1000 nm.7. The apparatus of in which the semiconducting material comprises AlZnOalloy claim 1 , x and y being positive integers.8. The apparatus of claim 1 , comprising a data processor to determine whether a neutron has been detected based on information derived from a charge induced on the ...

FISSILE NEUTRON DETECTOR

A fissile neutron detection system includes a neutron moderator and a neutron detector disposed proximate such that a majority of the surface area of the neutron moderator is disposed proximate the neutron detector. Fissile neutrons impinge upon and enter the neutron moderator where the energy level of the fissile neutron is reduced to that of a thermal neutron. The thermal neutron may exit the moderator in any direction. Maximizing the surface area of the neutron moderator that is proximate the neutron detector beneficially improves the reliability and accuracy of the fissile neutron detection system by increasing the percentage of thermal neutrons that exit the neutron moderator and enter the neutron detector. 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 system of wherein the thickness of the moderator arrangement is in a range from 1 cm to 5 cm.3. The fissile neutron ...

NEUTRON DETECTOR UNIT AND NEUTRON DETECTOR ARRANGEMENT

The invention relates to a neutron detector unit for neutrons, in particular thermal and cold neutrons, comprising a detector housing (), cathode elements and a plurality of anode elements (), wherein in order to form a volume detector unit the anode elements () and the cathode elements enable a three-dimensional spatial resolution for conversion events, characterised by a converter gas in the detector housing (). According to the invention, in a neutron detector arrangement which includes at least one neutron detector unit the neutron detector unit () or at least one of the neutron detector units () is oriented in such a way that at least some of the anode elements () of the at least one neutron detector unit () extend at least predominantly in a longitudinal orientation parallel or almost parallel to the direction of travel of the neutrons () to be detected. 142-. (canceled)43. A neutron detector unit for thermal and cold neutrons , comprising{'b': 7', '17', '27, 'a detector housing (, , ),'}cathode elements,{'b': 5', '15', '25, 'a plurality of wire-shaped anode elements (, , ), and'}{'b': 7', '17', '27, 'a converter gas in said detector housing (, , ),'}{'b': 7', '17', '27', '5', '15', '25', '5', '15', '25, 'wherein said neutron detector unit is a volume detector unit, in which a plurality of detector readout cells distributed three-dimensionally in the detector housing (, , ) are formed by at least some of said anode elements (, , ), or by at least some of said anode elements (, , ) and at least some of said cathode elements for the purposes of determining the position of conversion events,'}wherein said neutron detector unit is configured for determining the position by coincidence measurement, charge splitting or determining signal propagation times, andwherein the pressure of the converter gas in the detector housing is at or below a normal pressure.44. The neutron detector unit as claimed in claim 43 , wherein said converter gas contains at least one of the ...

ADVANCED THERMAL NEUTRON DETECTORS AND ASSOCIATED METHODS

A narrow thermal neutron detector includes a slidably receivable ionization thermal neutron detector module within an overall housing body. An active sheet layer of the ionization thermal neutron detector module can be tensioned across its width. The ionization thermal neutron detector module can include module upper major surface extents and module lower surface extents such that, when installed within the housing body, the module upper major surface extents are in a first spaced apart confronting relationship with housing upper major surface extents to define a first clearance and module lower major surface extents are in a second spaced apart confronting relationship with housing lower major surface extents to define a second clearance to accommodate housing flexing due to ambient pressure change. The housing body can be formed with a single opening for receiving the ionization thermal neutron detection module or with opposing first and second opposing end openings. 1. A thermal neutron detector for detecting thermal neutrons , said thermal neutron detector comprising:a main housing body defining first and second opposing end openings and a housing cavity therebetween;an ionization detector module having a peripheral outline that is complementary to the main housing body within the housing cavity and is slidably receivable in an installed position within the housing cavity, the ionization detector module having a length, a width and a height with the height being less than each of the length and the width and supporting an active sheet layer to span at least a majority of said length and width;an electrode arrangement including at least a first electrode and a second electrode within said main housing body in a spaced apart relationship with said active sheet layer, with the ionization detector module in the installed position, such that each of the first electrode and the second electrode is oppositely proximate to one of a pair of opposing major surfaces of 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, the thermal neutron detector arrangement further including at least one group of thermal neutron detectors with the thermal neutron detectors of each group in a side-by-side relationship and spaced apart in the side-by-side relationship to form a gap between adjacent ones of the thermal neutron detectors;a 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 ...

Device for measuring a neutron flux using a fissile substance

Method for detecting high-energy radiation using a low-voltage optimized ion chamber

Verfahren zum Messen eines hochenergetischen Strahlungsflusses, aufweisend: Anlegen einer Niederspannung an Elektroden in einer Ionenkammer, die mit einem Fluid gefüllt ist, das Ionen durch Wechselwirkung des Fluids mit der hochenergetischen Strahlung ausbilden kann, wobei die Niederspannung in einem Bereich von etwa 5 V bis etwa 20 V liegt und wobei das Fluid Bortrifluorid, Helium-3 und Lithium-6 aufweist; Messen eines Ionenstromsignals, das mit einem Ionenstrom in Beziehung steht, der durch die Niederspannung induziert wird; Bestimmen eines Leckstroms; Bestimmen einer Verstärkung; Bestimmung einer Größe des hochenergetischen Strahlungsflusses basierend auf dem Ionenstromsignal, der Verstärkung und dem Leckstrom; und Ausgeben des Ergebnisses der Größe des hochenergetischen Strahlungsflusses. A method of measuring a high energy radiant flux, comprising: Applying a low voltage to electrodes in an ion chamber filled with a fluid capable of forming ions by interaction of the fluid with the high energy radiation, wherein the low voltage ranges from about 5V to about 20V, and wherein the fluid comprises boron trifluoride, helium-3 and lithium-6; Measuring an ion current signal related to an ion current induced by the low voltage; Determining a leakage current; Determining a gain; Determining a magnitude of the high energy radiant flux based on the ionic current signal, the gain, and the leakage current; and Output the result of the size of the high-energy radiation flux.

Device for detection of slow neutrons

FIELD: instrument engineering.SUBSTANCE: invention relates to the detection of slow neutrons. Device for detecting a slow neutron contains the first converter of slow neutrons and the second converter of slow neutrons, interoperable with incident neutrons and electron generation, an electron multiplication and reading device located between the first slow neutron converter and the second converter of slow neutrons and made with the possibility of multiplying and reading electrons, and the device for multiplying and reading electrons contains the first cathode wire set, the second cathode wire set and the wire set of the reading electrode.EFFECT: technical result – increased detection efficiency of slow neutrons.9 cl, 7 dwg РОССИЙСКАЯ ФЕДЕРАЦИЯ (19) RU (11) (13) 2 676 952 C1 (51) МПК G01T 1/24 (2006.01) ФЕДЕРАЛЬНАЯ СЛУЖБА ПО ИНТЕЛЛЕКТУАЛЬНОЙ СОБСТВЕННОСТИ (12) ОПИСАНИЕ ИЗОБРЕТЕНИЯ К ПАТЕНТУ (52) СПК G01T 1/241 (2006.01) (21)(22) Заявка: 2017131586, 11.09.2017 (24) Дата начала отсчета срока действия патента: Дата регистрации: 11.01.2019 13.09.2016 CN 201610821372.X (56) Список документов, цитированных в отчете о поиске: RU 2102775 C1, 20.01.1998. CN (45) Опубликовано: 11.01.2019 Бюл. № 2 (54) УСТРОЙСТВО ОБНАРУЖЕНИЯ МЕДЛЕННЫХ НЕЙТРОНОВ (57) Реферат: Изобретение относится к обнаружению вторым преобразователем медленных нейтронов медленных нейтронов. Устройство обнаружения и выполненное с возможностью умножения и медленного нейтрона содержит первый считывания электронов, причем устройство преобразователь медленных нейтронов и второй умножения и считывания электронов содержит преобразователь медленных нейтронов, первый катодный проводной набор, второй выполненные с возможностью взаимодействия с катодный проводной набор и проводной набор падающими нейтронами и генерирования считывающего электрода. Технический результат электронов, устройство умножения и считывания - повышение эффективности обнаружения электронов, расположенное между первым медленных нейтронов. 8 з.п. ф-лы, ...

Device for measuring the intensity of a radiation of slow neutrons by means of ionization chamber

Differential ion chamber

Neutron detector system

A neutron detector unit and system comprising ion chamber and self-powered portions wherein signals from the ion chamber and self-powered portions are compared and the calibration of the ion chamber portion adjusted accordingly.

Small Ionization Camera

A Cavity Ionization Chamber comprising graphene electrode

본 발명은 챔버를 구성하는 전리함벽; 상기 챔버 내부 일정 면에 위치하는 고전압 전극; 및 상기 챔버 내부의 중심 영역에 위치하는 수집전극을 포함하며, 상기 고전압 전극은 그래핀 재질인 것을 특징으로 하는 공동 전리함에 관한 것이다. 공동전리함의 고전압 전극으로 그래핀을 사용함으로써, 고전압 전극의 금속두께에 따른 챔버 내부로 유입되는 방사선의 양이 감소하여 이온형성이 적어 저 에너지 방사선 측정이 어려워, 그래핀 전극의 특성이 초전도성과 초박막성을 갖는 전극으로 제작하면 방사선측정의 효율향상을 목적으로 도입된 그래핀 전극으로 구성된 공동전리조이다. The present invention relates to a chamber wall comprising a chamber wall; A high voltage electrode located on a predetermined surface in the chamber; And a collecting electrode located in a central region within the chamber, wherein the high voltage electrode is a graphene material. The use of graphene as a high-voltage electrode in a co-ionizer reduces the amount of radiation entering the chamber due to the thickness of the metal of the high-voltage electrode, making it difficult to measure low-energy radiation due to low ion formation, And a graphene electrode formed for the purpose of improving the efficiency of radiation measurement.

Neutron detector

Ion chambers - with improved linear response

Ion chamber in which the inner electrode is constructed from light material such as Ti or Zr to reduce heating, gas temperature and gas migration with consequent advantage to the linear response characteristic of the instrument. The basic construction can be varied by alternative forms of inner electrode such as hllow sealed cylinder or as a hollow cylinder with end seals forming a third gas sapce in conjunction with the gas interspace between the electrodes and the chamber used for evacuation and gas filling. The sizing of the inner electrode is critical in relation to the volume of the active gas space relative to the inactive gas space - the low heat and temperature factors promoting an advantageous linear response in both variants.

Neutron counters

1,240,379. Detecting neutrons. UNITED KINGDOM ATOMIC ENERGY AUTHORITY. 30 June, 1970 [1 July, 1969], No. 33290/69. Heading G6P. A neutron counter, employing the reaction consists of the tungsten anode wire, 10, supported in a boron trifluoride atmosphere within the aluminium tube 1. The wire 10 passes through the seal 6a and 6b in end plug 2. The extension 7 of the ceramic sleeve 6b provides an extended path for migrating joint braze material and for boron from the tube atmosphere so as to delay deterioration of the seal insulation. The wire 10 is tensioned by the spring 13a supported on the silicon disc 14.

Patent FR2056452A5

FISSION CHAMBER WITH SEGMENTED ANODE

Une chambre à fission, adaptée à être soumise à un bombardement neutronique, comporte, dans une enceinte 11, deux électrodes planes 12 et 13 parallèles soumises à une différence de potentiel prédéterminée ; l'une, 12, porte localement un dépôt d'actinide 14 en regard d'une zone locale de l'autre électrode, une borne de sortie de signal 22 étant connectée à cette autre électrode et un gaz ionisable occupant l'espace 16 entre ces électrodes ; ces électrodes s'étendent latéralement au-delà de la périphérie du dépôt 14 d'une distance A suffisante pour que le champ électromagnétique soit homogène entre la totalité du dépôt et la zone locale. L'électrode faisant face à l'électrode portant le dépôt d'actinide est composée d'une portion centrale 13A et d'une portion périphérique concentrique 13B isolées électriquement l'une vis-à-vis de l'autre en étant au moins approximativement au même potentiel, la portion centrale débordant latéralement de la zone locale d'une distance ?1 valant au plus le double de l'espace inter-électrode (H), la borne de sortie de signal (15) étant uniquement connectée à cette zone.

HIGH TEMPERATURE FISSION CHAMBER

L'invention concerne une chambre à fission comprenant : - une première partie formant un premier volume étanche au gaz et contenant : • un gaz de remplissage ; • au moins une couche d'un matériau fissile ; et - au moins deux électrodes électriquement isolées entre elles, lesdites électrodes étant tout ou partie contenues dans le premier volume, une électrode étant reliée à au moins un élément conducteur ; le gaz de remplissage étant du xénon. The invention relates to a fission chamber comprising: - a first part forming a first gas-tight volume and containing: • a filling gas; • at least one layer of fissile material; and - at least two electrodes electrically insulated from one another, said electrodes being all or part of the first volume, one electrode being connected to at least one conductive element; the filling gas being xenon.

Neutron detector - with cartesian coordinate beam position read out

Ionization chamber

Neutron flux measuring device

Patent FR2268353B1

Neutron detection device with ionization chamber and optical transduction comprising several optical cavities, each housing the free end of an optical fiber.

Dispositif de détection neutronique à chambre d’ionisation et à transduction optique comprenant plusieurs cavités optiques, logeant chacune l’extrémité libre d’une fibre optique. L’invention concerne un dispositif (1) de détection neutronique comprenant au moins une chambre d’ionisation étanche (2) et à transduction optique à plusieurs cavités dont le fonctionnement de chacune est basé sur la transduction optique à partir d’une fibre optique à l’extrémité libre au sein de la cavité, qui permet une mesure multipoint de flux neutronique, les points de mesures étant axialement distribués. Figure pour l’abrégé : Fig.2 Neutron detection device with ionization chamber and optical transduction comprising several optical cavities, each housing the free end of an optical fiber. The invention relates to a neutron detection device (1) comprising at least one sealed ionization chamber (2) and optical transduction with several cavities, the operation of each of which is based on the optical transduction from an optical fiber to the free end within the cavity, which allows multipoint neutron flux measurement, the measurement points being axially distributed. Figure for abstract: Fig.2

Improvements in processes and apparatus for counting neutrons

METHOD FOR LOCATING POSIONAL RADIONUCLEID, APPLICATIONS AND DEVICE FOR IMPLEMENTING THE SAME

Patent FR2247815B1

Patent FR2133798B1

Patent FR2124456A1

SUBMINIATURE FISSION CHAMBER WITH WATERPROOF PASSAGE

NEUTRON DETECTOR

L'INVENTION CONCERNE UN DETECTEUR DE NEUTRONS COMPRENANT UNE CHAMBRE D'IONISATION D POURVUE D'UNE ANODE 1 ET D'UNE CATHODE 2 POUR LA DETECTION D'UN FLUX DE NEUTRONS INJECTE DANS LA CHAMBRE, ET UN CABLE C COMPRENANT UN CONDUCTEUR CENTRAL 11 RELIE A L'ANODE OU A LA CATHODE ET UN CONDUCTEUR EXTERIEUR 14 RELIE A LA CATHODE OU A L'ANODE, CARACTERISE EN CE QU'IL EST PREVU UN CONDUCTEUR ANNULAIRE INTERMEDIAIRE 12 DISPOSE ENTRE LE CONDUCTEUR CENTRAL 11 ET LE CONDUCTEUR EXTERIEUR 14, ET ISOLE DE CES CONDUCTEURS, AINSI QUE DES CONDUCTEURS ANNULAIRES SUPERIEUR ET INFERIEUR 6 NOYES DANS DES ELEMENTS ISOLANTS 5, POUR SUPPORTER CELLE DES ELECTRODES QUI EST RELIEE AU CONDUCTEUR CENTRAL,LES CONDUCTEURS ANNULAIRES 6 ETANT RELIES ELECTRIQUEMENT ENTRE EUX ET LE CONDUCTEUR SUPERIEUR 6 ETANT CONNECTE AU CONDUCTEUR INTERMEDIAIRE 12. APPLICATION AUX REACTEURS NUCLEAIRES. THE INVENTION CONCERNS A NEUTRON DETECTOR INCLUDING AN IONIZATION CHAMBER D PROVIDED WITH AN ANODE 1 AND A CATHODE 2 FOR DETECTION OF A NEUTRON FLOW INJECTED INTO THE CHAMBER, AND A CABLE C INCLUDING A CENTRAL CONDUCTOR 11 CONNECTED TO THE ANODE OR TO THE CATHODE AND AN EXTERNAL CONDUCTOR 14 CONNECTED TO THE CATHODE OR TO THE ANODE, CHARACTERIZED IN THAT AN INTERMEDIATE ANNULAR CONDUCTOR 12 IS PROVIDED BETWEEN THE CENTRAL CONDUCTOR 11 AND THE EXTERNAL CONDUCTOR 14, AND INSULATE THESE CONDUCTORS, AS WELL AS THE UPPER AND LOWER ANNULAR CONDUCTORS 6 FLOODS IN INSULATING ELEMENTS 5, TO SUPPORT THAT OF THE ELECTRODES WHICH IS CONNECTED TO THE CENTRAL CONDUCTOR, THE ANNULAR CONDUCTORS 6 BEING ELECTRICALLY CONNECTED TO THE TOP AND THE 6 CONDUCTOR INTERMEDIATE CONDUCTOR 12. APPLICATION TO NUCLEAR REACTORS.

Nuclear radiation detector

Heavy isotope fissile fuel mixture - with breeder material content for use in neutron flux monitors

The mixture consists of >=1 heavy fissile isotope and >=1 heavy isotope which becomes fissile with exposure to neutron flux. The mixture is such that the fission cross section is approx. constant with time under a given neutron flux spectrum. The mixture contains 15-30% of U-235. It is either of U-234 and U-235 or of U-235 and U-238 of which 16% is U-235. Stable sensitivity is obtd. together with a long life.

HIGH TEMPERATURE FISSION CHAMBER

L'invention concerne une chambre à fission comprenant : - une première partie formant un premier volume étanche au gaz et contenant : • un gaz de remplissage ; • au moins une couche d'un matériau fissile ; et - au moins deux électrodes électriquement isolées entre elles, lesdites électrodes étant tout ou partie contenues dans le premier volume, une électrode étant reliée à au moins un élément conducteur ; le gaz de remplissage étant du xénon. The invention relates to a fission chamber comprising: a first part forming a first gas-tight volume and containing: • a filling gas; • at least one layer of fissile material; and - at least two electrodes electrically insulated from one another, said electrodes being all or part of the first volume, one electrode being connected to at least one conductive element; the filling gas being xenon.

Neutron-sensitive ionisation chambers

1308379 Ionization chambers LICENTIA PATENT-VERWALTUNGS GmbH 21 July 1970 [24 July 1970] 35288/70 Heading H1D A neutron-sensitive gas-filled ionization chamber for use in a boiling water nuclear reactor, is formed as a continuation of a coaxial cable. The outer conductor of the cable is stripped off the region A and a tube 5 is buttwelded to the cable sheath 2 at 6. A seal 7, rings of solder 12, and the inner conductor 4 of the chamber are fitted into the tube 5 and over the core 1 and the structure is exhausted, brought to soldering temperature, and filled with gas, after which the outer tube 5 is pinched at the front end and welded. The conductor 4 is coated with uranium applied electrolytically and the spacers 10 of aluminium oxide are applied by cathode sputtering. Apertures may be provided in the spacers 10 and in the aluminium oxide cylinder 11 to equalize gas pressure inside and outside the cylinder 4. The life of the chamber may be extended by including a fertile material or a poison. The seal may comprise a nickel tube 7 on which a layer 8 of aluminium oxide and a nickel layer 9 are deposited by cathode sputtering. Alternatively it may comprise a tube of aluminium oxide coated internally and externally with metal.

Gamma compensated neutron ion chamber

Proportional counter detecting neutrons in a gas including boron trifluoride are mounted in a container each with an anode wire held in the gas at preset pressure

Two neutron detection elements are mounted in a container (5), each with an anode wire held in the gas (boron trifluorane) at a preset pressure. The anode wires produce impulse signals corresponding to the number of neutrons present and are connected electrically in parallel. A signal integrated from the two impulse signals is transmitted from the container through a cable. The first and second elements are filled with gas at a pressure between 13332 Pa and 73326 Pa, preferably equal to about 33330 Pa. An additional means of neutron detection of different sensitivity may be installed inside a container which also holds the rest of the apparatus.

Fission ionization chamber

FIELD: nuclear energy technology. SUBSTANCE: compensation section electrode of fission ionization chamber has radiator made by uranium containing material and filter connected electrically with electrode at both sides of it. Compensation section radiator uranium content is (1+E) times more with respect to working section radiator content factor where E is relative absorption factor of fission products electron radiation while filter crossing through. Filter thickness is equal to splinters free path greatest value for filter material which is choosing electrically conductive with low activation cross-section. EFFECT: more effective monitoring of nuclear reactor operation. 1 dwg 6$$9140Сс ПЧ Го РОССИЙСКОЕ АГЕНТСТВО ПО ПАТЕНТАМ И ТОВАРНЫМ ЗНАКАМ (19) (51) МПК ВИ "” 2 076 339” Сл С ОЛТ 3/00, НО1 3 47/02 12) ОПИСАНИЕ ИЗОБРЕТЕНИЯ К ПАТЕНТУ РОССИЙСКОЙ ФЕДЕРАЦИИ (21), (22) Заявка: 93036386/25, 14.07.1993 (46) Дата публикации: 27.03.1997 (56) Ссылки: Дмитриев А.Б., Малышев Е К. Нейтронные ионизационные камеры для реакторной техники-- М.: Атомиздат, 1975, с. 65-70. Патент США М 4074764, кл. С 01 Т ЗЮ0, 1978. Патент США М 4086490, кл. С 0О1Т 1/18, 300, 1978. Малышев Е К. и др. Газоразрядные детекторы для контроля ядерных реакторов.- М.: Энергоатомиздат, ТЭЭЛ, с. 46-54. (71) Заявитель: Захаркин Игорь Иванович, Полионов Виктор Петрович, Сомов Иван Егорович (72) Изобретатель: Захаркин Игорь Иванович, Полионов Виктор Петрович, Сомов Иван Егорович (73) Патентообладатель: Захаркин Игорь Иванович, Полионов Виктор Петрович, Сомов Иван Егорович (54) ИОНИЗАЦИОННАЯ КАМЕРА ДЕЛЕНИЯ (57) Реферат: 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+=) большее, чем радиатор в рабочей секции, где = - ...

Electric switch with arc extinguishing by a flowing medium.

Radiation counter

Connection device for measurement device to measure neutron flux in test reactor, has set of maintenance units maintaining another set of maintenance units and fission chamber to realize electrical connection with exterior wall of chamber

The device has electrical connection units including a conducting connection socket (25) with ends for connecting an electrode (4) of a fission chamber (2) and a cable (10). A set of maintenance units are constituted by a conductive clamp (26) and an insulating insert and include a passage (29) for accommodating the electrical connection units. Another set of maintenance units are constituted by a sheath (24) for maintaining the former set of maintenance units and the fission chamber to realize an electrical connection with an exterior wall (6) of the fission chamber. Independent claims are also included for the following: (1) a device for realizing measurement in a test reactor (2) a method for realizing measurement in a test reactor.

Neutron-detecting ionization chamber with gamma ray compensation

Cette chambre comprend une électrode cylindrique à haute tension (1), une électrode cylindrique de transmission de signal (2) prélevant un courant de neutrons et une électrode cylindrique de compensation (3), qui sont disposées concentriquement en étant séparées les unes des autres, et une pluralité de trous (9) sont formés dans une partie de l'électrode (2) de transmission de signal, la surface totale des trous étant réglée à une valeur égale ou inférieure à 5 % de la surface totale de l'électrode de transmission de signal.Application notamment à la mesure du flux de neutrons en présence de rayons gamma dans un réacteur nucléaire.

RADIATION COUNTER

a. Compteur de radiations. b. Le compteur de radiations de l'invention comprend une électrode en un alliage contenant, en poids, plus de 30 % et moins de 90 % de nickel, le reste étant du chrome, du fer, etc et un gaz dont le composant principal est l'argon et qui est mélangé à au moins 2 % et à moins de 30 % en volume d'azote. Ce compteur fonctionne de façon stable à des températures dépassant 450 degrés C, produit un courant de sortie relativement intense et à un court temps de capture électronique. c. S'applique à la surveillance et au contrôle des réacteurs nucléaires, en particulier des réacteurs à refroidissement par gaz et des surgenérateurs.

Modular ionization chamber of the boron-coating type

A leak-tight cylindrical metal casing filled with an ionizable gas contains a plurality of modules each having the function of an independent ionization chamber. Electrically insulated resilient means serve to maintain each module in position both radially and longitudinally within the casing. A central cylindrical core within each module serves as a support for two concentric cylindrical electrodes whose opposite faces are coated with boron-10.

FIXED INCORE WIDE RANGE NEUTRON SENSOR

Disclosed is a neutron detector, provided with a sealed chamber having two spaced apart electrodes, hermetically sealed in the chamber with a seal which is located in an environment of at least two decades less neutron flux than that experienced by the detector. An ionizable gas is placed within the space between the electrodes, and pressurized to a pressure above one atmosphere. A layer of a mixture of an active material and a breeding material are positioned within the chamber, the active material and breeding material being respectively U-235 and U-234, which layer has a thickness of at least 0.2 milligrams per square centimeter.

Neutron detection device to measure the power of a nuclear reactor.

Patent JPS4964482A

PARTICLE DETECTOR AND MANUFACTURING METHOD THEREOF

L'INVENTION CONCERNE UN DETECTEUR DE PARTICULES, NOTAMMENT DE NEUTRONS, AINSI QU'UN PROCEDE DE FABRICATION D'UN TEL DETECTEUR. LE DETECTEUR COMPORTE UN CORPS EN ALUMINE FRITTEE, REALISE EN UNE SEULE PIECE PAR MOULAGE, DANS LEQUEL SONT NOYEES DEUX ELECTRODES TUBULAIRES CONCENTRIQUES DEFINISSANT ENTRE ELLES UNE CHAMBRE A FISSION. LA CHAMBRE A FISSION EST OBTENUE PAR FLUIDIFICATION D'UN PRODUIT NORMALEMENT RIGIDE, QUE L'ON EVACUE PAR UN EVENT REALISE DANS LE CORPS LORS DU MOULAGE, CET EVENT ETANT ENSUITE REFERME A L'AIDE D'UN LASER PAR FUSION D'UN BOUCHON EN ALUMINE. APPLICATION A LA REALISATION DE DETECTEURS PEU ENCOMBRANTS ET POUVANT SUPPORTER DE HAUTES TEMPERATURES AINSI QU'UN FLUX DE PARTICULES ELEVE.

COMPONENT CLEANING AGENTS WITH IMPROVED CRACK RESISTANCE

Improvements relating to the counting of neutrons

In a neutron counter using radiative capture, the (n, y) reaction provides radioactive isotopes emitting beta and gamma radiation. The reaction takes place within a Geiger-Muller type counter which detects the internally induced beta and gamma radiation. The counter has a halogen gas filling and comprises concentric electrodes, incorporating the rhodium isotope Rh 103, which after neutron activation produces Rh 104 and Rh 104 m. The first decays with a beta emission and a half-life of 44 seconds and the second has a gamma emission and a half-life of 264 seconds.

Double-section gas-filled ionization chamber

FIELD: neutron detectors, in particular, measuring neutron flows in current channels of reactor control systems, critical assemblies and other neutron sources. SUBSTANCE: device has housing 1 which contains two electrode systems 2 and 3 which provide two sensitive chambers V1 4 and V2 5 which heights are L1 and L2, respectively. First chamber is filled with gas mix or gas under pressure P1. Said gas mix or gas emits ions in reaction with neutrons. Second chamber V2 is filled with gas mix or gas under pressure of P2. Said gas mix or gas does not emit ions in reaction with neutrons. Absolute value of nominal electric power supply of second sensitive chamber provides complete current compensation for γ radiation and is not greater than , absolute value of nominal power supply voltage of first sensitive chamber. Another claim of invention describes device design in which pressure P2 belongs to another given interval. In this case absolute value of nominal power supply voltage of second sensitive chamber, which provides complete current compensation for γ radiation, is not greater than , absolute value of nominal power supply voltage of first sensitive chamber up to absolute value of electric strength of insulation or maximal permissible power supply voltage . All electrodes are insulated from housing by means of support insulators 6. One electrode 7 in first and second sections is insulated from other electrodes; it is high-voltage electrode used for connection through electric terminals 8 and electric line 9 to external nominal voltage power supply 10. Two other signal electrodes are electrically closed and are designed for connection to electric current meter 11. Design of chamber provides possibility to make samples which are compensated for γ radiation current; their thermal neutron detection sensitivity is greater than that of chambers with solid boron-containing radiator by factor of 4-8. They may be used in current channels for measuring thermal neutron flow in ...

Neutron detector

A neutron detector comprises a gas-filled dielectric shell, preferably a glass balloon, having opposite electrodes. An electric field is established whereby ionizing particles may be detected via ionization and current flow in the gas, using a pulse height analyzer or other conventional means. The dielectric shell preferably has low gas permeability and a bulk resistivity in the range of 10 8 to 10 17 Ω-m, and is preferably in the millimeter to centimeter size range. Multiple balloons may be arranged in parallel or may be individually addressable by the detector electronics.

Bar detergents with improved tear resistance

Counter

Neutron detector for use within nuclear reactor

49,787 ABSTRACT OF THE DISCLOSURE An improved long operating lifetime ionization chamber type neutron detector for use within a nuclear reactor. The chamber contains uranium U-235 as the neu-tron sensitive material and helium or argon fill gas. The atom rate of U-235 to fill gas is from 0.45 to 1.8 for helium, and 2.3 to 9 for argon.

Patent JPS6160394B2

Extension of the length of life of neutron - detectors

Nuclear radiation detectors

1468260 lonization detector WESTING- HOUSE ELECTRIC CORP 17 June 1974 [27 June 1973] 26659/74 Heading H1D To increase the working life of a proportional neutron counter the gas filled envelope, the neutron absorbing lining of which emits short range ionizing radiation which dissociates the polyatomic component of the filler gas forming products which contaminate the neutron absorber, is connected to a surrounding gas reservoir shielded from the short range radiator. Al envelope 12 with 0À06 inch lining of <SP>10</SP>B 18 absorbing thermal neutrons, and insulated central W wire 0À004-0À010 inch diameter and at high voltage is coupled via holes 26 to concentric gas reservoir 28 having a volume at least as large as envelope 12. Li and alpha particles from layer 18 cannot penetrate wall 12. The filler gas is Ar with 5% v/v CO 2 ; pressure within the stated range 2- 200 Torr is typically 20 Torr. In an alternative design (Figs. 2, 3 not shown), multiple envelopes are enclosed within and communicate with one reservoir. The whole counter may optionally be surrounded by a thermalizing moderator 32. Other neutron absorbent material may be substituted for the <SP>10</SP>B.

Device for measuring the intensity of a beam of slow neutrons by means of an ionization chamber

Enhancements to diversion chambers

The invention relates in particular to a highly effective detector allowing two-dimensional analysis of a flux of neutral particles emitted by a source 1 and passing through an object 2. This detector comprises a stack 4 consisting of elements arranged in grazing incidence with respect to the mean direction 3 of the particles, and affording both the function of converter and of charge guide. Application to imaging.

Neutron detector

Increasing sensitivity of radiochromatographic analyser - by use of grid above cathode

Substance to be analysed is placed on a chromatographic plate after addition of isotope emitting alpha- and alpha-radiation, and is observed with scintillation detector. The samples placed on a cathode surface, with a grid parallel to it and on anode spaced from the grid. The cathode is at a negative potential, pref. -10 to -500V, w.r.t. the grid. Sensitivity to low energy emission is increased.

Patent JPS5824746B2

Radiation detector of elongated length with electrode support assembly therefor

A radiation detection device having a plurality of tubular concentric electrode assemblies positioned end to end within a housing wherein the tubular electrode assemblies are supported by an electrode support assembly comprised of a plurality of electrode support members positioned at the ends of the tubular electrode assemblies so as to space the concentric electrodes and also provide insulation therebetween. The electrode supports are also provided with a plurality of extending ball-like members from the outer periphery of the electrode supports resiliently mounted within the electrode support to accurately position the electrode assemblies within the housing, provide good electrical contact between the housing and the electrode support and also permit ease of removal of the entire assembly from the housing without damage to the components or casing.

NEUTRON DETECTOR TUBE, ITS MANUFACTURING PROCESS

La modification de la forme de l'enveloppe tubulaire d'un détecteur de neutrons à gaz permet sa transformation en un tube adapté à la prospection des champs neutroniques de large surface dans une direction de propagation déterminée. La modification consiste en une simple opération d'aplatissement de la région médiane du tube-enveloppe. Elle n'entraîne que peu de frais d'investissement et de main-d'oeuvre. Le nouveau détecteur est utilisable pour la détection de neutrons et, de préférence pour celle des neutrons se déplaçant dans des champs de grande ampleur. Modifying the shape of the tubular envelope of a gas neutron detector allows it to be transformed into a tube suitable for prospecting large-area neutron fields in a determined direction of propagation. The modification consists of a simple operation of flattening the middle region of the casing tube. It does not involve much investment and labor costs. The new detector can be used for the detection of neutrons and, preferably for that of neutrons moving in large fields.

Long life proportional counter radiation detector

A long life gas-filled proportional counter radiation detector is provided having a shielded gas reservoir interconnected with the prime detection chamber. The gas fill within the detection chamber is exposed to radiation but the reservoir gas is shielded to thereby minimize dissociation and absorption of the gas upon the chamber wall.

Counter tube for radiation detection

Patent FR2268353A1

Method for detecting high-energy radiation using low voltage optimised ion chamber

Radiation detector made from titanium or zirconium

Method and device for monitoring neutron flux of nuclear reactor

(57)【要約】本公報は電子出願前の出願データであるた め要約のデータは記録されません。

Real-time multiplicity counter

A neutron multi-detector array feeds pulses in parallel to individual inputs that are tied to individual bits in a digital word. Data is collected by loading a word at the individual bit level in parallel. The word is read at regular intervals, all bits simultaneously, to minimize latency. The electronics then pass the word to a number of storage locations for subsequent processing, thereby removing the front-end problem of pulse pileup.

Nuclear radiation detector - contg. gaseous isotope and functioning as geiger counter with high sensitivity to neutrons and gamma rays

The appts. consists of a sealed chamber (1) contg. at least one anode and cathode (2,3) across which a difference in positive potential is applied. Chamber (1) is filled by a gas mixt. where at least one gas (G1) contains at least one nucleus sensitive to neutrons. The gas mixt. also contains at least one rare gas (G2) and an auto-chopper (G3); and the detector functions as a Geiger-Muller counter. Gas (G1) is pref. He-3; or gaseous cpds. of B-10; Li-6; U; or Pu; whereas gas (G2) is He, Ne, Ar, Kr or Xe; and gas (G3) is the halogens or their cpds., or organic cpds. The potential difference between electrodes (2,3) is pref. max. 1500 volts. The pressure of gas (G1) pref. provides the detector with the same sensitivity to neutrons and gamma-rays.

DEVICE FOR MEASURING THE SPATIAL INTENSITAETS DISTRIBUTION OF NUCLEAR RADIATION WITH A GAS DISCHARGE RADIATION DETECTOR

Patent FR1572385A

Patent FR2423862B1

Miniature insulated fission chamber

Imager

Time interval adjustment system

Patent FR2247815A1

DEVICE FOR CONNECTING A FISSION CHAMBER

MINIATURE FISSION CHAMBER, OF THE PULSE TYPE IN PARTICULAR LIKELY TO OPERATE AT HIGH TEMPERATURE (

Patent FR2235479A1

Wire spark chamber with magnetostrictive readout

A wire spark chamber having magnetostrictive readout. One embodiment thereof is for particular use with low energy gamma rays, X-rays, or neutral particles whose presence is detected by secondary particles produced in converters placed in or around the wire planes of the chamber. Another embodiment has a very large and uniformly sensitive detecting area by means of auxiliary conducting planes which serve to charge the chamber capacity with a low impedance transmission-line characteristic. The embodiment for use with low energy gamma, X-ray or neutral particles has utilization in the field of medical diagnostics while the large chamber embodiment provides the capability of detecting multiple tracks with uniform high efficiency, thus fulfilling a long looked for need in the field of wire spark chambers.

Particle detector.

Wide range neutron detection system

A neutron detection system is described which is operable over a wide range of neutron flux levels. The system includes a fission type ionization chamber neutron detector, means for gamma and alpha signal compensation, and means for operating the neutron detector in the pulse counting mode for low neutron flux levels, and in the direct current mode for high neutron flux levels.