Синтетический материал для обнаружения ультрафиолетового излучения и/или рентгеновского излучения

FIELD: chemical industry. SUBSTANCE: invention relates to chemical industry; it can be used when manufacturing devices for security systems or for detecting ultraviolet and/or X-ray radiation, for example, sensors, indicators or detectors. Material is characterized with the following formula (I): , in which M' is a combination of at least two mono-atomic cations of various alkali metals selected from Li, Na, K and Rb containing 0-98 mol. % of Na cation; M'' is trivalent mono-atomic cation of metal selected from Al, Ga, B or a combination of any of them with trivalent mono-atomic cation of a transition element of groups 3-10 of Periodic table of chemical elements of International Union of Pure and Applied Chemistry (hereinafter – IUPAC); M''' is mono-atomic cation of an element of group 14 of Periodic table of chemical elements of IUPAC or any combination thereof; X is anion of an element selected from S, Se, Te, F, Cl, Br and I, or any combination thereof; M'''' is doping cation of an element selected from rare-earth or transition metals of Periodic table of chemical elements of IUPAC, for example, Eu, Tb, Ti, V, Cr, Mn, Fe, Co, Ni, Cu and Zn, or any combination thereof, or M'''' is absent. For example, material characterized by the formula (I) is (Na,K) 8 Al 6 Si 6 O 24 (Cl,S) 2 , (Na,Rb) 8 Al 6 Si 6 O 24 (Cl,S) 2 , (Na,K,Rb) 8 Al 6 Si 6 O 24 (Cl,S) 2 , (Na,K) 8 Al 6 Si 6 O 24 (Cl,S) 2 :Eu, (Na,K) 8 Al 6 Si 6 O 24 (Cl,S) 2 :Tb, (Li,K) 8 Al 6 Si 6 O 24 (Cl,S) 2 , (Li,Rb) 8 Al 6 Si 6 O 24 (Cl,S) 2 , (Li,K,Rb) 8 Al 6 Si 6 O 24 (Cl,S) 2 or (Li,Na,K,Rb) 8 Al 6 Si 6 O 24 (Cl,S) 2 . To determine the intensity of ultraviolet and/or X-ray radiation, the specified material is subjected to radiation, the change in material color is determined, for example, visually and compared to comparison sample. EFFECT: invention provides for material stability for a long time. 18 cl, 6 dwg, 4 ex РОССИЙСКАЯ ФЕДЕРАЦИЯ (19) RU (11) (13 ...

ANALYTISCHES MATERIAL ZUR DOSIMETRIE IONISIERENDER STRAHLEN

Verfahren und Vorrichtung zur Messung der Eindringtiefe einer Strahlung

Fibre optic ionizing radiation detector

The ionizing radiation detector comprises an optical fibre, and a detection system 14 to sense radiation induced luminescence emitted from both ends of the fibre. The optical fibre can be spooled, to provide a discrete detector or the optical fibre can be installed around an area to provide an integrated detector. To calibrate the fibre to allow for radiation induced increase of attenuation, a second, identical, optical fibre is subjected to the same environment and its attenuation is measured between source 16 and detector 15. A third detector 18 may monitor the output of source 16. The fire may be similar to a conventional optreal communication fibre having a core surrounded by a sheath of lower refractive index. ...

Direct skin radiation dose measurement system with quantitative optical read-out

Colour changing materials sensitive to UV or ionizing radiation (i.e. radiochromic) are used oin a flexible adhesive patch attached to the skin. Calibration regions are included in addition to at least one functional cell. A camera is used to capture images of the function in addition to any calibration reference regions. An algorithm converts a digital picture obtained into a dose map of the functional colour changing region of the patch, providing in-vivo real time dosimetry.

DOSIMETER FOR THE COLLECTION OF RADIATION UNDER UTILIZATION OF THE RADIO PHOTO LUMINESCENCE

Thick radiation sensitive devices

Radiation dosage indicator

METHOD AND APPARATUS FOR DETECTING RADIATION

FIBER OPTIC RADIOCHROMIC DOSIMETER PROBE AND METHOD TO MAKE THE SAME

A fiber optic dosimeter probe for sensing radiation dose including an optical fiber having a free end and a sensitive end, a window having a sensitive side and a rear side; a radiation sensitive layer between the sensitive end of the optical fiber and a sensitive side of the window, the radiation sensitive layer being made of a material having an optical property that changes with absorbed radiation dose, an amount of the material corresponding to a predetermined sensitivity to radiation; wherein the window and the optical fiber have a near water equivalent interaction with radiation and are MR compatible.

RADIOCHROMIC LEUKO DYE REAL TIME DOSIMETER, ONE WAY OPTICALWAVEGUIDE

Appareil de mesure des radiations d'énergie élevée

ANALYTIC MATERIAL FOR THE DOSIMETRY OF IONIZING ONES RAYS.

HIGH RESOLUTION IMAGING USING OPTICALLY TRANSPARENT PHOSPHORS

On forme des images en exposant des verres (42) luminescents, optiquement transparents et optiquement stimulables, comportant des centres luminescents et des centres pièges, à un rayonnement ionisant modelé. Les images sont immédiatement lisibles, par scintillation, ou peuvent être stockées dans les verres pour lecture ultérieure, lecture rendue possible par un déblocage, stimulé optiquement (14), des charges stockées.

Дозиметр ионизирующих излучений

FIELD: measuring. SUBSTANCE: invention relates to sensors and apparatuses for determining ionising emissions and/or ionising particles. A dosimeter containing a sensory element made in the form of a bimetallic strip made of materials with different coefficients of radiation alteration of the elasticity modulus, a bending strain measuring apparatus, a shape recovery apparatus, according to the invention, the bending strain measuring apparatus is made in the form of a capacitive sensor connected with the capacitance meter, wherein the capacitive sensor constitutes a variable capacitance capacitor, one of the plates whereof is attached on the end of the sensory element normally to the surface thereof, the plates of the variable capacitance capacitor are made in the form of circles of equal areas, the capacitance meter is made with a dose processing and recording unit precalibrated for measuring various types of emission separately or jointly according to the predetermined types of emission, the shape recovery apparatus is made in the form of a current source connected to two connection terminals of one of the current-conducting materials of the bimetallic strip. EFFECT: invention ensures measurement of the value of the ionising dose of emission in the form of an electrical capacitance signal and recording thereof. 4 cl, 1 dwg РОССИЙСКАЯ ФЕДЕРАЦИЯ (19) RU (11) (13) 2 756 394 C1 (51) МПК G01T 1/06 (2006.01) ФЕДЕРАЛЬНАЯ СЛУЖБА ПО ИНТЕЛЛЕКТУАЛЬНОЙ СОБСТВЕННОСТИ (12) ОПИСАНИЕ ИЗОБРЕТЕНИЯ К ПАТЕНТУ (52) СПК G01T 1/06 (2021.05) (21)(22) Заявка: 2020126379, 05.08.2020 (24) Дата начала отсчета срока действия патента: 30.09.2021 Приоритет(ы): (22) Дата подачи заявки: 05.08.2020 (45) Опубликовано: 30.09.2021 Бюл. № 28 2 7 5 6 3 9 4 R U (54) Дозиметр ионизирующих излучений (57) Реферат: Изобретение относится к датчикам и устройствам для определения ионизирующих излучений и/или ионизирующих частиц. Дозиметр, содержащий чувствительный элемент, выполненный в виде бипластины из ...

ПЕРСОНАЛЬНЫЙ И ТЕРРИТОРИАЛЬНЫЙ САМОПОКАЗЫВАЮЩИЙ ПРЕДУПРЕЖДАЮЩИЙ РАДИАЦИОННЫЙ ДОЗИМЕТР МОМЕНТАЛЬНОГОДЕЙСТВИЯ

... 1. Устройство для дозиметрического контроля, содержащее подложку, имеющую нанесенный на нее чувствительный к излучению материал, содержащий средство для продления срока хранения, по меньшей мере один визуализирующий слой, содержащий указанный чувствительный к излучению материал, обладающий способностью к проявлению детектируемого изменения цвета при экспозиции ионизирующему излучению с энергией более 5 эВ. 2. Устройство по п.1, отличающееся тем, что содержит средство для защиты чувствительного к излучению материала от нежелательного воздействия излучения, имеющего уровень энергии, по меньшей мере настолько высокий, как у ультрафиолетового света, выбранное из группы, состоящей из УФ-абсорбера, УФ-отражателя или слоя, непрозрачного для излучения. 3. Устройство по любому из пп.1 и 2, отличающееся тем, что содержит чувствительный к излучению материал, обладающий способностью к проявлению детектируемого изменения цвета при экспозиции ионизирующему излучению, выбранный из группы, состоящей из ...

УСТРОЙСТВО И СПОСОБ ДЛЯ ОБНАРУЖЕНИЯ ИЗЛУЧЕНИЯ

... 1. Устройство для обнаружения и картографирования излучения, испускаемого радиоактивными материалами, содержащее полимерный сердечник, расположенный внутри внешней оболочки, при этом сердечник представляет собой кубический, цилиндрический, сферический или усеченный сферический сердечник и содержит по меньшей мере один чувствительный к гамма-излучению, испускаемому радиоактивными материалами, компонент, а внешняя оболочка содержит коллимационный кожух. ! 2. Устройство по п.1, в котором внешняя оболочка имеет такую же форму, что и сердечник. ! 3. Устройство по п.1, которое имеет усеченную сферическую форму с диаметром в диапазоне 5-20 см. ! 4. Устройство по п.1, в котором полимерный материал сердечника содержит по меньшей мере эпоксидную смолу или полиуретан. ! 5. Устройство по п.1, в котором материал сердечника содержит материал с изменением цвета, который может содержать по меньшей мере одно лейкосоединение флуорана или ди- или триарилметановый краситель, причем лейкосоединение может содержать ...

Dosimeter zum Messen von Strahlungsdosen mit einem Messelement aus einem unter Strahlungseinwirkung seinen Farbton aendernden Glas

FIBRE OPTIC IONISING RADIATION DETECTOR

Device and method for the detection and mapping of radiation

A device for the detection and mapping of radiation comprises a polymeric core 1 (e.g. a sheet, cube, cylinder or sphere) incorporating at least one radiation sensitive component, wherein the core is located within an external shell comprising a collimation sheath 2 which may be metallic (e.g. lead). The method for the detection and mapping of radiation comprises; placing the device in a location to be investigated, exposing the device to radiation for a predetermined length of time, removing the device from the location, removing the polymeric core from the external shell, and analysing the polymeric core to obtain an image of the radiation sources. The device does not require an electrical supply and it may be used to 3-dimensionally map the location, intensity and identity of radiological hazards via deployment in sites such as; active cells, gloveboxes, other active plants and confined spaces with high radiation backgrounds.

Improvements in or relating to dosimeters

... 1,115,809. Detecting neutrons. ELECTROSPACE CORPORATION. 11 May, 1966 [16 July, 1965], No. 20916/66. Heading G6P. In a dosimeter, neutron and gamma ray intensities are measured respectively by a solid state diode and a radio photoluminescent glass member. Both are mounted together in a cylindrical case and the glass member has a lead and bronze shield which serves to reduce the response peaks inherent in the glass. The bronze lowers the effect of the lead K-absorption edge, producing a flatter characteristic. The glass member is silver activated phosphate glass and a silicon diode is employed. The gamma ray measurement is effected by luminescent light emitted from the glass upon the application of ultra-violet light and the neutron flux measurement is made in an electric circuit connected to the diode output terminals.

PROCEDURE FOR THE SPECTROMETRIC PHOTON DOSIMETRY FOR RÖNTGENUND GAMMA RADIATION

NUCLEAR RADIATION MEASURING APPARATUS AND METHOD

NUCLEAR RADIATION MEASURING APPARATUS AND METHOD ABSTRACT OF THE DISCLOSURE A visually readable nuclear radiation measurement device functioning as a dose rate meter or a dosimeter. There are disclosed several embodiments allowing the user to match the brightness of a scintillating means to a reference light source thereby to ascertain the desired dose rate radiation information and allowing the user to match the brightness of light penetrating a dye type dosimeter to a reference light source to ascertain the total dose.

FIBER OPTIC RADIOCHROMIC DOSIMETER PROBE AND METHOD TO MAKE THE SAME

A fiber optic dosimeter probe for sensing radiation dose including an optical fiber having a free end and a sensitive end, a window having a sensitive side and a rear side; a radiation sensitive layer between the sensitive end of the optical fiber and a sensitive side of the window, the radiation sensitive layer being made of a material having an optical property that changes with absorbed radiation dose, an amount of the material corresponding to a predetermined sensitivity to radiation; wherein the window and the optical fiber have a near water equivalent interaction with radiation and are MR compatible.

RADIATION DOSAGE INDICATOR

DEVICE TO MEASURE AN AMOUNT OF RADIATION

SELF-INDICATING RADIATION ALERT DOSIMETER

Described as a self-indicating instant radiation dosimeter (1001) for monitoring high energy radiations, such as X-ray. The dosimeter contains a radiation sensitive, color changing, indicating composition (10), e.g., a diacetylene (R-C=C-C=C-R', where R and R' are substituents groups) or a radiochromic dye, a polymeric binder (20) and optionally a shelf life extender (50) or an activator (40). The radiation sensitive composition (10) changes color instantly when exposed to high energy radiation. The dose is estimated by comparing the color with a color reference chart or more accurately with a spectrophotometer or an optical densitometer. The radiation sensitive composition (10) is protected from low energy radiation such as UV light, by a layer of low energy absorbing materials, such as UV absorbers.

DETECTOR FOR A UV FALSE POSITIVE RADIATION SENSITIVE DEVICES

Disclosed is a detector for monitoring a UV false positive from genuine X-ray positive of color developing radiation sensitive devices. A layer which can be scratched off and is opaque to undesired radiation but transparent to X-ray is printed on the sensor. If the sensor displays a signal (i.e., develops color), whether it is genuine or false positive can be confirmed by scratching off the opaque layer. If the signal is a genuine positive, the whole sensor will be uniformly exposed/colored including the area under the opaque layer. If it is a false positive, the area under the scratched off layer will be of lighter color than the rest of the sensor.

Environment dependent—temperature independent color changing label

A timing device comprises a sensing material and/or a component which is sensitive to the presence of an environmental attribute. The environmental attribute drives and speeds up or slows the timing device as the concentration of the attribute increases or decreases, respectively. Alternatively, the timing device is activated upon sensing the presence of the environmental attribute and indicates a total passage of time from exposure/activation of the timing device. Particularly, sensing materials of varying types are able to be used to indicate exposure to a variety of substances. For example, in some embodiments, the timing device comprises a sensing material which is sensitive to the presence of ultraviolet radiation. Alternatively, the sensing material is sensitive to other variables such as x-ray radiation and nuclear radiation. In further embodiments, the sensing material is sensitive to biological or physical contamination.

PERSONAL AND SELF INDICATING RADIATION ALERT DOSIMETER

Described is a self-indicating instant radiation dosimeter () for monitoring high energy radiations, such as X-ray. The dosimeter contains a radiation sensitive, color changing, indicating composition (), e.g., a diacetylene (R—C≡C—C≡C—R′, where R and R′ are substituents groups) or a radiochromic dye, a polymeric binder () and optionally a shelf life extender () or an activator (). The radiation sensitive composition () changes color instantly when exposed to high energy radiation. The dose is estimated by comparing the color with a color reference chart or more accurately with a spectrophotometer or an optical densitometer. The radiation sensitive composition () is protected from low energy radiation such as UV light, by a layer of low energy absorbing materials, such as UV absorbers. 125-. (canceled)26. A color changing radiation sensitive device comprising:i) a sensor comprising radiation sensitive material sandwiched between two transparent plastic clear films;ii) a piece of the said sensor sandwiched between an opaque substrate and clear protective UV absorbing film.27. A device of further comprising at least one color reference bar.28. A device of further sandwiched between two substrates.29. A device of wherein the radiation sensitive material is a diacetylene.30. The device of wherein said diacetylene has at least one set of conjugated alkynes and is selected from the group consisting of: R′—C≡C—C≡C—R″ claim 29 , where R′ and R″ are independently selected from: (CH)—H; (CH)OH; (CH)—OCONH—R; (CH)—O—CO—R; (CH)—O—R; (CH)—COOH; (CH)—COOM; (CH)—NH; (CH)—CONHR; (CH)—CO—O—Ror a mixture thereof; where b=1-10 claim 29 , and M is a cation or (R)N wherein Ris substituted or unsubstituted alkyl or phenyl; and symmetrical or asymmetrical fatty acid of R—(CH)C≡C—C≡C—(CH)—Ror their derivatives claim 29 , where at least one of the Ror Ris —COOH and n and m are independently selected from 1-10.311. A process of making a radiation sensitive device by cutting a sensor of claim ...

Patent RU2018141221A3

Patent RU2018141227A3

Способ изготовления кремниевого рентгеношаблона

FIELD: physics. SUBSTANCE: invention can be used for making a silicon X-ray image. Essence of the invention consists in that the method includes processes of preliminary selection of plane-parallel silicon plates, sputtering of conductive adhesive sublayers from light (i.e. with low atomic weight) metals on the working surface of the silicon plate (substrate), formation on the working surface of the resistive mask, electrodeposition of the X-ray absorbing masking layer from heavy metals through the resistive mask, its subsequent removal and formation of the support ring and the template support membrane by partial removal of the silicon plate central part from its back side by etching, formation of support ring and template bearing membrane is performed by means of plasma-chemical etching through stencil or pre-formed directly on rear side of plate protective mask, stencil and protective mask should be made of materials characterized by relatively low rate of etching compared to silicon, for example, aluminum or its alloys. EFFECT: technical result is simplification of X-ray fabrication. 1 cl, 4 dwg РОССИЙСКАЯ ФЕДЕРАЦИЯ (19) RU (11) (13) 2 716 858 C1 (51) МПК G01T 1/06 (2006.01) G03B 42/02 (2006.01) ФЕДЕРАЛЬНАЯ СЛУЖБА ПО ИНТЕЛЛЕКТУАЛЬНОЙ СОБСТВЕННОСТИ (12) ОПИСАНИЕ ИЗОБРЕТЕНИЯ К ПАТЕНТУ (52) СПК G01T 1/06 (2019.08); G03B 42/02 (2019.08) (21)(22) Заявка: 2019112195, 22.04.2019 (24) Дата начала отсчета срока действия патента: 17.03.2020 Приоритет(ы): (22) Дата подачи заявки: 22.04.2019 (56) Список документов, цитированных в отчете о поиске: RU 2488910 C1, 27.07.2013. RU 2469369 C2, 10.12.2012. US 6379871 B1, 30.04.2002. US 20130148788 A1, 13.06.2013. US 7608367 B1, 27.10.2009. JP 2005175406 A, 30.06.2005. (45) Опубликовано: 17.03.2020 Бюл. № 8 2 7 1 6 8 5 8 R U (54) Способ изготовления кремниевого рентгеношаблона (57) Реферат: Использование: для изготовления кремниевого травлением центральной части кремниевой рентгеношаблона. Сущность изобретения пластины с ее тыльной ...

Roentgendosimeter

Strahlungsindikator aus Kunststoff und ein Verfahren zu seiner Herstellung

ANZEIGEGERÄT FÜR DIE STRAHLENDOSIS

Dosimeter to energy and direction-independent fairs from quantum radiation and procedure to its production

HIGHLY SOLUBLE ILLUSTRATION BY OPTICALLY TRANSPARENCIES PHOSPHORUS COMPLEXES

THICK RADIATION SENSITIVE DEVICES

Synthetic material for detecting ultraviolet radiation and/or X-radiation

The invention relates to a material represented by the following formula (I), (M') ...

Radiation dosimetry method and associated apparatus

DOSIMETER

A dosimeter comprising a support having provided thereon a radiation-sensitive layer which comprises (a) a polymer containing halogen atoms or a polymer containing acetic acid groups and (b) a pH-sensitive indicator dye. the dosimeter provides an easy determination of exposure dose by color change, even at high and law exposure doses.

ANALYTICAL MATERIAL FOR THE DOSIMETRY OF IONIZING RAYS

RADIATION DETECTION MATERIAL AND METHOD TO DETECT RADIATION USING SAME

The purpose of the present invention is to provide a radiation detection material including a salt including an amylose molecule and an iodide ion. According to the present invention, the radiation detection material is able to easily determine whether neutrons, gamma rays, beta rays, electron beams, ultraviolet, and the like are radiated. The method is able to estimate a strength of the emitted radiation using the radiation detection material groups by controlling an amount of a reducing agent. The method has an effect capable of easily determining whether the radiation is emitted. The radiation detection material comprises: a response to generate a radiation resolvent including one or more types among OH radicals and H_2O_2 by disassembling and radiating the radiation to H_2O; a response to oxidize the radiation resolvent with the iodide ion and a molecular iodine; a response to generate a tree-iodide by reacting the molecular iodine (I_2) with the iodide ion; and a response to enable ...

RADIATION DOSIMETRY METHOD AND ASSOCIATED APPARATUS

L'invention porte sur un procédé et l'appareil associé de mesure de l'exposition au rayonnement à compensation de température du détecteur, et de mesure des variations du matériau radiosensible du dosimètre utilisé. Le procédé recourt à un radiodosimètre comportant, déposée sur un substrat, une couche d'un matériau radiosensible dont l'absorbance optique varie: en fonction du niveau d'exposition, de la longueur d'onde et également de la température. La couche radiosensible est faite d'une substance sensiblement imperméable au rayonnement. Le procédé consiste à exposer ladite couche à une dose de rayonnement, à en mesurer optiquement l'absorbance spectrale sur une plage de longueurs d'onde, à examiner ladite absorbance pour déterminer la coordonnée d'absorbance et la coordonnée de longueur d'onde d'un point donné d'une courbe d'absorbance spectrale de la couche exposée, puis à déterminer la valeur de la dose de rayonnement reçue, laquelle est fonction des coordonnées d'absorbance et de longueur ...

RADIATION DOSAGE INDICATOR

A multi-ply radiation dosage indicator (10), and method of manufacture, is disclosed including a first ply (12) having visible indicia (14) thereon and a second ply (16) having a radiation sensitive zone (18) overlying the indicia (14) of the first ply (12). The radiation sensitive zone (18) is capable of changing opacity in response to exposure to a radiation dosage exceeding a predetermined threshold so as to change the visibility of the indicia (14) thereby providing an indication as to whether the indicator (10) has become irradiated. An optical filter ply (26) may be provided overlying the indicia (14), and the indicator (10) also may be provided with a transparent protective outer ply (19). A pressure sensitive adhesive ply (30) having a removable release sheet (32) is employed for attaching the indicator (10) to a substrate.

Radiation dosimetry method and associated apparatus

A method and associated apparatus for monitoring exposure to radiation, with compensation for temperature variation of a sensor and variations in the amount of radiation sensitive material in a dosimeter used in the method. The method utilizes a radiation dosimeter having a layer of radiation sensitive material on a substrate, the radiation sensitive material having an optical absorbance which varies in accordance with degree of radiation exposure and wavelength and which also varies in dependence on temperature. The radiation sensitive layer includes a substantially radiation impervious substance. The method comprises exposing the layer of radiation sensitive material to a dose of radiation, optically measuring a spectral absorbance of the exposed layer of radiation sensitive material within a range of wavelengths, examining the measured spectral absorbance of the exposed layer of radiation sensitive material to determine an absorbance coordinate and a wavelength coordinate of a predetermined ...

Radiation dosimeter

A radiation dosimeter for preparing a dosage map of a specific rotary canister of a blood radiating machine. This dosimeter includes a sandwich assembly of a first panel and a second panel and a gamma ray-sensitive film disposed therebetween, for mounting temporarily in the canister during gamma ray dosage and canister rotation.

Detector for a UV false positive of radiation sensitive devices

Disclosed is a detector for monitoring a UV false positive from genuine X-ray positive of color developing radiation sensitive devices. A layer which can be scratched off and is opaque to undesired radiation but transparent to X-ray is printed on the sensor. If the sensor displays a signal (i.e., develops color), whether it is genuine or false positive can be confirmed by scratching off the opaque layer. If the signal is a genuine positive, the whole sensor will be uniformly exposed/colored including the area under the opaque layer. If it is a false positive, the area under the scratched off layer will be of lighter color than the rest of the sensor.

METHOD FOR THE SPECTROMETRIC PHOTON DOSIMETRY FOR X-RAY AND GAMMA RADIATION

Dosimeter zur akkumulierten Dosisbestimmung von Gamma- und Neutronenstrahlung

Glass materials for silver-activated phosphate glass dosimeter

Radiation badge-dosimeter glass consists, in parts by weight, of: lithium metaphosphate LiPO3, 40-55; aluminium metaphosphate Al(PO3)3, 60-45 complemental to LiPO3; and based on LiPO3+Al(PO3)3, by weight: silver metaphosphate AgPO3, 2-11%; and optionally, magnesium metaphosphate Mg(PO3)2 or beryllium metaphosphate Be(PO3)2, 1.5-5%. A small amount (5%) of alumina or silica may be present. After irradiation with q - or X-rays, the glass fluoresces when exposed to U.V. radiation. For rapid determination of radiation, the irradiated glass may be heated to 90-110 DEG C. for 10 minutes. A known Ba-K-Al-Ag glass is referred to.ALSO:Radiation badge-dosimeter glass consists, in parts by weight, of: lithium metaphosphate LiPO3, 40-55; aluminium metaphosphate Al(PO3)3, 60-45 complemental to LiPO3; and, based on LiPO3+Al(PO3)3, by weight: silver metaphosphate AgPO3, 2-11%; and optionally, magnesium metaphosphate Mg(PO3)2 or beryllium metaphosphate Be(PO3)2, 1.5-5%. After irradiation with g - or X-rays ...

PROCEDURE AND DEVICE FOR THE MEASUREMENT OF THE RADIATION DEPTH OF A RADIATION

Dosimeter, device for determining the radiation dose received, and methods for producing the same

THICK RADIATION SENSITIVE DEVICES

Described is radiation sensitive imaging and dosimeter composition (20) containing a radiation sensitive material (21), e.g., a diacetylene (R-C=C-C=C- R', where R and R' are substituent groups) or a radiochromic dye, a polymeric binder (22) and optionally a solvent (23) and/or an activator (24). Radiation sensitive materials are incorporated into a moldable or castable material and are molded or casted into shaped-articles (100), such as coatings, films, fiber, plaques, rods and blocks. Upon exposure to high-energy radiations, radiation sentitive material develops color thereby producing a visible image. Because of the higher thickness, a significantly lower dose of radiation can be monitored and an image is produced in three dimensions. Materials, processes and usages for thick radiation sensitive devices are described. A thick block can be used for monitoring radiation dosages in the three dimensions.

NOVEL RADIATION DETECTOR

The invention provides a device for the detection and mapping of radiation, the device comprising a polymeric core located within an external shell material, wherein the polymeric core comprises at least one radiation sensitive component and the external sheath comprises a collimation sheath. Preferably, the polymeric core comprises a spherical core which is encased within the external shell. The external shell is preferably comprised of a metal, most preferably lead or tungsten. The invention also provides a method for the detection and mapping of radiation in a location, which comprises: (a) placing a device according to the invention in the location to be investigated; (b) allowing the device to remain in the location and be exposed to the radiation for a predetermined length of time; (c) removing the device from the location; (d) removing the polymeric core from the external shell; and (e) analysing said polymeric core by means of an optical analysis technique applying a software-based image reconstruction algorithm in order to determine the location, form and intensity of said radiation. The device and method of the invention facilitate the detection and mapping of radiation, and find particular use in mapping the location, intensity and identity of radiological hazards in 3 dimensions in sites such as active cells, gloveboxes, other active plants and confined spaces. Advantages over the prior art include the lack of requirement for an electrical supply, and the ability to deal with high radiation backgrounds and to be deployed in confined or restricted spaces.

SELF-INDICATING RADIATION ALERT DOSIMETER

Described as a self-indicating instant radiation dosimeter (1001) for monitoring high energy radiations, such as X-ray. The dosimeter contains a radiation sensitive, color changing, indicating composition (10), e.g., a diacetylene (R-C=C-C=C-R', where R and R' are substituents groups) or a radiochromic dye, a polymeric binder (20) and optionally a shelf life extender (50) or an activator (40). The radiation sensitive composition (10) changes color instantly when exposed to high energy radiation. The dose is estimated by comparing the color with a color reference chart or more accurately with a spectrophotometer or an optical densitometer. The radiation sensitive composition (10) is protected from low energy radiation such as UV light, by a layer of low energy absorbing materials, such as UV absorbers.

Environment dependenttemperature independent color changing label

A timing device comprises a sensing material and/or a component which is sensitive to the presence of an environmental attribute. The environmental attribute drives and speeds up or slows the timing device as the concentration of the attribute increases or decreases, respectively. Alternatively, the timing device is activated upon sensing the presence of the environmental attribute and indicates a total passage of time from exposure/activation of the timing device. Particularly, sensing materials of varying types are able to be used to indicate exposure to a variety of substances. For example, in some embodiments, the timing device comprises a sensing material which is sensitive to the presence of ultraviolet radiation. Alternatively, the sensing material is sensitive to other variables such as x-ray radiation and nuclear radiation. In further embodiments, the sensing material is sensitive to biological or physical contamination.

PHOTONIC POLYMER MULTILAYERS FOR COLORIMETRIC RADIATION SENSING

A radiation sensor includes a substrate and a polymer multilayer film including alternating layers of a high refractive index polymer and a low refractive index polymer. The high refractive index polymer and the low refractive index polymer each comprise repeat units derived from a photo-crosslinkable monomer. The radiation sensors are useful in preparing various articles, including wearable patches, packaging materials, labels, and window panes. Also described is a method of detecting radiation using the radiation sensors. 1. A radiation sensor comprising ,a substrate;a polymer multilayer film comprising alternating layers of a high refractive index polymer and a low refractive index polymer;wherein the high refractive index polymer comprises repeat units derived from a first photo-crosslinkable monomer; and{'sub': 1-12', '1-12, 'wherein the low refractive index polymer consists of repeat units derived from a second photo-crosslinkable monomer and at least one monomer selected from the group consisting of Calkyl (meth)acrylates, Caryl (meth)acrylates, macromeric (meth)acrylates, (meth)acrylic acids, alpha olefins, vinyl esters, vinyl alkyl ethers, styrenic monomers, fluorinated monomers, and combinations thereof.'}2. The radiation sensor of claim 1 , wherein the substrate is glass.3. The radiation sensor of claim 1 , wherein the substrate is a flexible substrate.4. The radiation sensor of claim 3 , wherein the flexible substrate is a poly(ethylene terephthalate) substrate.5. The radiation sensor of claim 1 , wherein the polymer multilayer film comprises at least 2 to 50 alternating layers.6. The radiation sensor of claim 1 , wherein the high refractive index polymer layers and the low refractive index polymer layers each independently have thicknesses of 0.01 to 0.2 micrometers.7. The radiation sensor of claim 1 , wherein the high refractive index polymer has a refractive index greater than 1.5.8. The radiation sensor of claim 1 , wherein the high refractive index ...

METHOD FOR THE SPECTROMETRIC PHOTON DOSIMETRY FOR X-RAY AND GAMMA RADIATION

GLASS DOSE MEASURING METHOD AND APPARATUS THEREFOR

PURPOSE: To measure an exposure dose with high sensitivity and high accuracy by reducing the fluorescence component inherent to a fluorescent glass element and selectively taking in a fluorescence pulse component of a specific wavelength region where the fluorescence corresponding to an exposure dose appears most largely. CONSTITUTION: One of optically diffracted ultraviolet pulses is applied to a radiation exposure fluorescent glass element 15 and the other one of them is applied to a standard fluorescent glass element 17 through a translucent mirror 14 and a reflecting mirror 16 and the exposure fluorescence pulses generated from the respective fluorescence detection surfaces of both elements 15, 17 are sent to photomultiplier tubes 22, 23 while specific wavelength ranges are selected (20, 21) and the exposure fluorescence pulses are sent to a sampling gate circuits 27, 28 while the standard fluorescence pulses are sent to a sampling gate circuit 30. The exposure and standard fluorescence ...

Люминесцентный материал

FIELD: chemical industry.SUBSTANCE: invention relates to the chemical industry and can be used in the manufacture of light-emitting devices, such as lighting devices, as well as display elements, fluorescent tubes, security systems, and visualization or diagnostics systems. The luminescent material is characterized by the following formula:in which М' is monatomic cation Li, K, Rb; or a combination of at least two cations of alkali metals containing 0-98 mol. % of Na cation; М'' is a trivalent monoatomic cation of an element selected from В, Al, Ga, Cr, Mn, Fe, Со, Ni и Cu, or any combination thereof; М''' is a monoatomic cation of an element selected from Si, Ge, Zn, N, As и Ga, or any combination thereof; X is an anion of an element selected from F, Cl, Br и I, or any combination thereof; or X is missing; X' is an anion of an element selected from Group 16 of the Periodic Table of Chemical Elements of the International Union of Pure and Applied Chemistry, or any combination thereof, or X' is missing; M'''' is a cation of an element selected from Ti, V, Cr, Mn, Fe, Со, Ni, Cu и Zn, or any combination thereof, provided X and/or X' is present. For example, the luminescent material represented by the Formula (I) is (Li,Na)8(AlSi)6O24(Cl,S)2:Ti, (Na,K)8(AlSi)6O24(Cl,S)2:Ti or (Na,Rb)8(AlSi)6O24(Cl,S)2:Ti.EFFECT: specified luminescent material does not contain expensive rare-earth elements and environmentally hazardous heavy metals, emits white light and provides a long-lasting glow - for at least 50 hours.18 cl, 4 ex, 2 dwg

Способ ретроспективной оценки поглощенных доз гамма-излучения по образцам сенсорных экранов смартфонов при аварийных радиологических ситуациях

Изобретение относится к области дозиметрии. В способе ретроспективной оценки поглощенных доз гамма-излучения при аварийных радиологических ситуациях в качестве дозиметра используется образец стекла экрана смартфона той же модели, что и у лица, подвергшегося неконтролируемому радиационному воздействию, размером 5×5 мм. В лабораторных условиях образец подвергается радиационному воздействию и измерению сигнала электронного парамагнитного резонанса (ЭПР). Затем строится график зависимости ЭПР-сигнала от накопленной дозы облучения. Далее от дозиметра, находившегося у лица, подвергшегося неконтролируемому радиационному заражению, отделяется образец размером 5×5 мм, который выводится из зоны облучения на 48 ч и в течение 120 ч с момента выведения из зоны облучения, выполняется измерение (ЭПР). По измеренному сигналу и по построенному графику определяется радиационное воздействие. Технический результат – определение радиационного воздействия на организм человека, попавшего в аварийную радиологическую ...

Люминесцентный материал

РОССИЙСКАЯ ФЕДЕРАЦИЯ (19) RU (11) (13) 2018 141 227 A (51) МПК C01B 17/45 (2006.01) C01B 33/32 (2006.01) C01G 15/00 (2006.01) C01G 17/00 (2006.01) C01F 7/02 (2006.01) C09K 11/08 (2006.01) ФЕДЕРАЛЬНАЯ СЛУЖБА F21K 2/00 (2006.01) ПО ИНТЕЛЛЕКТУАЛЬНОЙ СОБСТВЕННОСТИ B42D 25/387 (2014.01) A61B 5/00 (2006.01) F21W 111/00 (2006.01) (12) ЗАЯВКА НА ИЗОБРЕТЕНИЕ (21)(22) Заявка: 2018141227, 23.05.2016 (71) Заявитель(и): ТУРУН ИЛИОПИСТО (FI) Приоритет(ы): (30) Конвенционный приоритет: (43) Дата публикации заявки: 10.06.2020 Бюл. № 16 (72) Автор(ы): ЛАСТУСААРИ Мика (FI), НОРРБО Исабелла (FI) (86) Заявка PCT: FI 2016/050349 (23.05.2016) (87) Публикация заявки PCT: A WO 2017/194825 (16.11.2017) Адрес для переписки: 191036, Санкт-Петербург, а/я 24 "НЕВИНПАТ" R U (57) Формула изобретения 1. Материал, представленный следующей формулой (I): A 2 0 1 8 1 4 1 2 2 7 (54) Люминесцентный материал 2 0 1 8 1 4 1 2 2 7 (85) Дата начала рассмотрения заявки PCT на национальной фазе: 10.12.2018 R U 09.05.2016 FI 20165392 в которой М' представляет собой моноатомный катион Li, или моноатомный катион K, или моноатомный катион Rb; или комбинацию по меньшей мере двух моноатомных катионов разных щелочных металлов, выбранных из группы 1 Периодической системы химических элементов ИЮПАК, где указанная комбинация содержит 0-98 мол. % моноатомного катиона Na; М'' представляет собой трехвалентный моноатомный катион элемента, выбранного из группы 13 Периодической системы химических элементов ИЮПАК, или переходного элемента, выбранного из любой из групп 3-12 Периодической системы химических элементов ИЮПАК, или любую комбинацию таких катионов; М''' представляет собой моноатомный катион элемента, выбранного из группы 14 Периодической системы химических элементов ИЮПАК, или элемента, выбранного из любой из групп 13 и 15 Периодической системы химических элементов ИЮПАК, или из Zn, или любую комбинацию таких катионов; X представляет собой анион элемента, выбранного из группы 17 Периодической системы химических ...

Verfahren und Vorrichtung zur Messung der Strahlungstiefe einer Strahlung

The invention pertains to a measurement device comprising two sensors for measuring radiation doses. The sensors are, for example, optical waveguides aligned along a straight line. One of the optical waveguides covers a longer section along the line than the other waveguide; in particular, the difference is at least 20 mm. Measurement using the measurement device is done as follows: the radiation dose along the line of radiation down to the expected penetration depth is measured using the wider sensor; the narrower sensor is used to determine the radiation dose in a volume element within the radiation path. A quotient is formed from the two measurements and used to calculate the radiation depth on the basis of reference values. The proposed device facilitates rapid and simple determination of a penetration depth of an ionising radiation, for example in tissue.

Novel radiation detector

POLYMER FILMS

Improvements in or relating to glass composition

... 726,813. Glass manufacture. PITTSBURGH PLATE GLASS CO. Nov. 14, 1952 [Nov. 14, 1951], No. 28753/52. Class 56. A glass which exhibits a change in colour or transparency on irradiation with short waves such as gamma or X-rays and which thus provides a rough quantitative indication of the total radiation to which it has been exposed consists in percentages by weight of SiO 2 , 39- 80; sodium, potassium or rubidium oxides or combinations thereof, 10-23 and barium or strontium oxides or a combination thereof, 5- 45.5. The glass is kept free from impurities, particularly cerium, iron, titanium and antimony oxides which greatly reduce the change of colour which varies from light blue to purple depending on the exposure. The addition of up to 2 per cent P 2 O 5 whilst reducing the sensitivity gives a red tinge which may sometimes be more easily perceptible. A preferred composition is SiO 2 , 39.1; K 2 O, 15.5 and BaO, 45.4. The glass may be used as a direct reading radiation dosimeter by workers ...

Phosphate glass for x-ray, gamma-ray and thermal neutron dosimeters

Glass for use in X-ray, V-ray, and thermal neutron dosimeters having a base of oxygenated compounds of phosphorus and including silver as activator has a composition comprising, by weight, Li2O, 0-10%; BeO, 5-15%; Na2O, 0.1-10%; Al2O3, 0.1-10%; Ag2O, 1.5-10%; and P2O5, 71.8-80.6%, the balance, if any, consisting of compatible ingredients.

Apparatus and method for detecting radiation exposure levels

Method and apparatus for detection and monitoring of radiation exposure are disclosed, utilising photoexcitable storage phosphors and reading apparatus in a number of configurations for use in homeland security, emergency response and medical fields. In one form, apparatus comprises a portable dosimeter device adapted to receive and multiple phosphor elements to allow population screening in event of mass exposure. Further forms for medical use include insertable probes and adhesive phosphor patches for use in detecting radiation exposure in medical therapy or imaging.

Luminescent material

The invention relates to a material rep- resented by the following formula (I). Further, the invention relates to a luminescent material, to different uses, and to a device.

NUCLEAR RADIATION MEASURING APPARATUS AND METHOD

RADIOCHROMIC LEUKO DYE REAL TIME DOSIMETER, ONE WAY OPTICALWAVEGUIDE

Abstract of the Disclosure A radiochromic leuko dye dosimeter includes a plastic tube containing a solution of a radiochromic dye which is sensi-tive to ionizing radiation, one end of the tube being closed by a reflective surface, the opposite end of the tube being closed by a transparent plug to form a one-way optical waveguide. Light enters the tube through the transparent end thereof and is reflected back and exits through the transparent end. The intensity of the exiting light is measured to determine radiation induced absorption of the leuko dye.

NUCLEAR RADIATION MEASURING APPARATUS AND METHOD

PERSONAL AND AREA SELF-INDICATING INSTANT RADATION ALERT DOSIMETER

Described as a self-indicating instant radiation dosimeter (1001) for monitoring high energy radiations, such as X-ray. The dosimeter contains a radiation sensitive, color changing, indicating composition (10), e.g., a diacetylene (R-C=C-C=C-R', where R and R' are substituents groups) or a radiochromic dye, a polymeric binder (20) and optionally a shelf life extender (50) or an activator (40). The radiation sensitive composition (10) changes color instantly when exposed to high energy radiation. The dose is estimated by comparing the color with a color reference chart or more accurately with a spectrophotometer or an optical densitometer. The radiation sensitive composition (10) is protected from low energy radiation such as UV light, by a layer of low energy absorbing materials, such as UV absorbers.

RADIATION DOSIMETER

A radiation dosimeter for preparing a dosage map of a specific rotary canister of a blood radiating machine. This dosimeter (14) includes a sandwich assembly of a first panel (16) and a second panel (18) and a gamma ray-sensitive film (20) disposed therebetween, for mounting temporarily in the canister (12) during gamma ray dosage and canister rotation.

Glass with phosphates for dosemeter with rays chi, gamma and neutrons thermal

Process for the determination of a size proportional to the proportioning of a quantum radiation low in energy

Glass with phosphates for dosemeter with rays chi and gamma

A radionuclide detector based on multi-array plastic scintillator and the radiation detect method using it

A radionuclide detector based on multi-array plastic scintillator and the radiation detect method using it

Two window indicator

This present disclosure provides a multi-ply radiation dosage indicator, which includes a first ply having two visible readable indicia thereon. The dual radiation sensitive zones are capable of changing opacity in response to exposure radiation. Each radiation sensitive zone can respond to an irradiation dose in tandem or independent of one another. Once the radiation sensitive zone exceeds the design exposure threshold, the visibility of the indicia is altered thereby providing an indication of irradiation exposure. The radiation sensitive zone may either be transparent or opaque and can change its opacity in response to exposure to radiation exceeding a predetermined threshold so as to change the visibility of the indicia.

ПЕРСОНАЛЬНЫЙ И ТЕРРИТОРИАЛЬНЫЙ САМОПОКАЗЫВАЮЩИЙ ПРЕДУПРЕЖДАЮЩИЙ РАДИАЦИОННЫЙ ДОЗИМЕТР МОМЕНТАЛЬНОГО ДЕЙСТВИЯ

Предложенная группа изобретений относится к средствам для дозиметрического контроля для мониторинга дозы излучения высокой энергии с использованием чувствительных к излучению материалов. Первый вариант устройства для дозиметрического контроля содержит подложку, имеющую нанесенный на нее по меньшей мере один визуализирующий слой, содержащий композицию, состоящую из связующего, чувствительного к излучению материала и добавки для продления срока хранения, обладающей способностью к проявлению детектируемого изменения цвета при экспозиции ионизирующему излучению с энергией более 5 эВ. Второй вариант устройства для дозиметрического контроля содержит подложку, имеющую нанесенный на нее чувствительный к излучению материал, содержащий по меньшей мере один визуализирующий слой, содержащий указанный чувствительный к излучению материал, обладающий способностью к проявлению детектируемого изменения цвета при экспозиции ионизирующему излучению с энергией более 5 эВ, и индикатор, способный указывать на ложный положительный сигнал или ложные показания. Способ изготовления устройства для дозиметрического контроля заключается в том, что изготавливают слоистый материал, для чего ламинируют совместно с подложкой визуализирующий слой, содержащий связующее и чувствительный к излучению материал, обладающий способностью к проявлению детектируемого изменения цвета при экспозиции ионизирующему излучению с энергией более 5 эВ. Техническим результатом от реализации изобретения является создание дозиметра, который изменяет свой цвет при воздействии ионизирующего излучения, но не подвержен воздействию окружающей среды, в том числе влажности, повышенной температуре, солнечному свету и т.д. 3 н. и 15 з.п. ф-лы, 28 ил., 10 табл. ÐÎÑÑÈÉÑÊÀß ÔÅÄÅÐÀÖÈß RU (19) (11) 2 345 384 (13) C2 (51) ÌÏÊ G01T 1/04 (2006.01) ÔÅÄÅÐÀËÜÍÀß ÑËÓÆÁÀ ÏÎ ÈÍÒÅËËÅÊÒÓÀËÜÍÎÉ ÑÎÁÑÒÂÅÍÍÎÑÒÈ, ÏÀÒÅÍÒÀÌ È ÒÎÂÀÐÍÛÌ ÇÍÀÊÀÌ (12) ÎÏÈÑÀÍÈÅ ÈÇÎÁÐÅÒÅÍÈß Ê ÏÀÒÅÍÒÓ (21), (22) Çà âêà: 2005129994/28, 26.02.2004 (72) Àâòîð(û): ÏÀÒÅËÜ ...

Способ дозиметрии гамма-излучения

FIELD: dosimetry.SUBSTANCE: method for gamma radiation dosimetry comprises stages of placing a fibre optic waveguide with a core of pure quartz glass in the gamma radiation area and measuring the changes in the radiation-induced optical losses in the fibre optic waveguide (RIOLW), wherein the dose rate of gamma radiation is calibrated by the RIOLW measured at the wavelength of the probing radiation of 1.55 mcm, wherein the glass of the waveguide core has an oxygen deficiency and comprises no more than 0.01 mass.% of chlorine.EFFECT: increase in the accuracy of dosimetry of zones with a high level of gamma radiation.2 cl, 1 tbl

Синтетический материал для обнаружения ультрафиолетового излучения и/или рентгеновского излучения

РОССИЙСКАЯ ФЕДЕРАЦИЯ (19) RU (11) (13) 2018 141 221 A (51) МПК C09K 11/64 (2006.01) ФЕДЕРАЛЬНАЯ СЛУЖБА ПО ИНТЕЛЛЕКТУАЛЬНОЙ СОБСТВЕННОСТИ (12) ЗАЯВКА НА ИЗОБРЕТЕНИЕ (21)(22) Заявка: 2018141221, 08.05.2017 (71) Заявитель(и): ТУРУН ИЛИОПИСТО (FI) Приоритет(ы): (30) Конвенционный приоритет: 09.05.2016 FI 20165392 (85) Дата начала рассмотрения заявки PCT на национальной фазе: 10.12.2018 R U (43) Дата публикации заявки: 10.06.2020 Бюл. № 16 (72) Автор(ы): ЛАСТУСААРИ Мика (FI), НОРРБО Исабелла (FI) (86) Заявка PCT: (87) Публикация заявки PCT: WO 2017/194834 (16.11.2017) R U (54) Синтетический материал для обнаружения ультрафиолетового излучения и/или рентгеновского излучения (57) Формула изобретения 1. Материал, представленный следующей формулой (I): A 2 0 1 8 1 4 1 2 2 1 A Адрес для переписки: 191036, Санкт-Петербург, а/я 24, "НЕВИНПАТ" 2 0 1 8 1 4 1 2 2 1 FI 2017/050355 (08.05.2017) в которой М' представляет собой комбинацию по меньшей мере двух моноатомных катионов разных щелочных металлов, выбранных из группы, состоящей из Li, Na, K и Rb; М'' представляет собой трехвалентный моноатомный катион элемента, выбранного из группы 13 Периодической системы химических элементов ИЮПАК, или переходного элемента, выбранного из любой из групп 3-12 Периодической системы химических элементов ИЮПАК, или любую комбинацию таких катионов; М''' представляет собой моноатомный катион элемента, выбранного из группы 14 Периодической системы химических элементов ИЮПАК, или любую комбинацию таких катионов; X представляет собой анион элемента, выбранного из группы 16 Периодической системы химических элементов ИЮПАК, или любую комбинацию таких анионов, или X представляет собой анион элемента, выбранного из группы, состоящей из F, Cl, Br и I, или любую комбинацию таких анионов; и Стр.: 1 A 2 0 1 8 1 4 1 2 2 1 R U A Стр.: 2 2 0 1 8 1 4 1 2 2 1 где параметры имеют следующие значения: у = интенсивность цвета [процент черного], А1 = амплитуда цвета, х = величина УФ-индекса для солнечного цвета или ...

FLUORESZENZGLASDOSIMETER.

LANGGESTRECKTER FORMKOERPER ZUR ERFASSUNG DER OERTLICHEN DOSIS ENERGIEREICHER STRAHLUNG

HIGH RESOLUTION IMAGING USING OPTICALLY TRANSPARENT PHOSPHORS

Images are formed by exposing optically transparent, optically stimulable luminescent glasses (42) including luminescent centers and trapping centers, to patterned, ionizing radiation. The images may be read immediately, using scintillation, or may be stored in the glasses for subsequent reading using optically stimulated (14) detrapping of stored charges.

RADIATION DOSAGE INDICATOR

A multi-ply radiation dosage indicator (10), and method of manufacture, is disclosed including a first ply (12) having visible indicia (14) thereon and a second ply (16) having a radi-ation sensitive zone (18) overlying the indicia (14) of the first ply (12). The radiation sensitive zone (18) is capable of chang-ing opacity in response to exposure to a radiation dosage ex-ceeding a predetermined threshold so as to change the visibility of the indicia (14) thereby providing an indication as to whether the indicator (10) has become irradiated. An optical filter ply (26) may be provided overlying the indicia (14), and the indica-tor (10) also may be provided with a transparent protective ou-ter ply (19). A pressure sensitive adhesive ply (30) having a rem-ovable release sheet (32) is employed for attaching the indicator (10) to a substrate.

DISPOSITIF POUR MESURER UNE DOSE DE RADIATION

LA PRESENTE INVENTION CONCERNE UN DISPOSITIF POUR MESURER UNE DOSE DE RADIATION EN UTILISANT LE CHANGEMENT DE L'ABSORBANCE DE LA LUMIERE D'UN MATERIAU TRANSPARENT LORS D'UNE IRRADIATION. SELON L'INVENTION, IL COMPREND SENSIBLEMENT UNE SOURCE DE LUMIERE 3, UNE UNITE EMETTANT UNE LUMIERE MONOCHROMATIQUE 4, UNE UNITE POUR CONTROLER LA QUANTITE DE LUMIERE, UNE UNITE DE MONTAGE D'UN ECHANTILLON 5, UNE UNITE DE DETECTION 6 ET UNE UNITE D'INDICATION 8, LA SOURCE DE LUMIERE ETANT UNE LAMPE A CATHODE CREUSE. L'INVENTION S'APPLIQUE NOTAMMENT A LA MESURE DE DOSES DE FAISCEAUX D'ELECTRONS OU DE RAYONS GAMMA.

Improvements with the compositions of glass

MATERIAU ANALYTIQUE POUR LA DOSIMETRIE DE RAYONNEMENTS IONISANTS

LE MATERIAU CONSISTE EN DES FEUILLES DE TEREPHTALATE DE POLYETHYLENE AYANT UNE DENSITE DE 1,393 A 1,397GCM, UNE EPAISSEUR DE FEUILLE DE 991MM, UNE RESISTANCE A LA TRACTION DE 20010NMM, UN ALLONGEMENT DE 10010, UNE CRISTALLINITE DE 551,5 ET UN RETRAIT THERMIQUE A 1,5.

VIEWING DEVICE LEVEL OF IRRADIATION

L'invention a pour objet un dispositif de visualisation de niveau d'irradiation d'un élément soumis à un rayonnement ionisant, comprenant une structure de détection de radiations (3), dite structure radiosensible, dans un intervalle donné de doses absorbées, dit intervalle de fonctionnement, comprenant au moins une couche radiochromique (4).

A DETECTOR FOR A UV FALSE POSITIVE OF RADIATION SENSITIVE DEVICES

Disclosed is a detector for monitoring a UV false positive from genuine X-ray positive of color developing radiation sensitive devices. A layer which can be scratched off and is opaque to undesired radiation but transparent to X-ray is printed on the sensor. If the sensor displays a signal (i.e., develops color), whether it is genuine or false positive can be confirmed by scratching off the opaque layer. If the signal is a genuine positive, the whole sensor will be uniformly exposed/colored including the area under the opaque layer. If it is a false positive, the area under the scratched off layer will be of lighter color than the rest of the sensor.

THICK RADIATION SENSITIVE DEVICES

Described is radiation sensitive imaging and dosimeter composition (20) containing a radiation sensitive material (21), e.g., a diacetylene (R-C=C-C=C-R', where R and R' are substituent groups) or a radiochromic dye, a polymeric binder (22) and optionally a solvent (23) and/or an activator (24). Radiation sensitive materials are incorporated into a moldable or castable material and are molded or casted into shaped-articles (100), such as coatings, films, fiber, plaques, rods and blocks. Upon exposure to high-energy radiations, radiation sentitive material develops color thereby producing a visible image. Because of the higher thickness, a significantly lower dose of radiation can be monitored and an image is produced in three dimensions. Materials, processes and usages for thick radiation sensitive devices are described. A thick block can be used for monitoring radiation dosages in the three dimensions.

THICK RADIATION SENSITIVE DEVICES

POLYMER FILMS AND THEIR USE

OPTICAL DOSIMETER

Apparatus and method for detecting radiation exposure levels

Method and apparatus for detection and monitoring of radiation exposure are disclosed, utilising photoexcitable storage phosphors and reading apparatus in a number of configurations for use in homeland security, emergency response and medical fields. In one form, apparatus comprises a portable dosimeter device adapted to receive and multiple phosphor elements to allow population screening in event of mass exposure. Further forms for medical use include insertable probes and adhesive phosphor patches for use in detecting radiation exposure in medical therapy or imaging.

FIBER OPTIC RADIOCHROMIC DOSIMETER PROBE AND METHOD TO MAKE THE SAME

A fiber optic dosimeter probe for sensing radiation dose including an optical fiber having a free end and a sensitive end, a window having a sensitive side and a rear side; a radiation sensitive layer between the sensitive end of the optical fiber and a sensitive side of the window, the radiation sensitive layer being made of a material having an optical property that changes with absorbed radiation dose, an amount of the material corresponding to a predetermined sensitivity to radiation; wherein the window and the optical fiber have a near water equivalent interaction with radiation and are MR compatible. 1. A fiber optic dosimeter probe for sensing radiation dose comprising:an optical fiber having a free end and a sensitive end, a window having a sensitive side and a rear side;a radiation sensitive layer between said sensitive end of said optical fiber and a sensitive side of said window, said radiation sensitive layer being made of a material having an optical property that changes with absorbed radiation dose, an amount of said material corresponding to a predetermined sensitivity to radiation;wherein said window and said optical fiber have a near water equivalent interaction with radiation and are MR compatible.2. The probe as claimed in claim 1 , wherein said window is at least one of a substrate layer claim 1 , a flexible window claim 1 , a reflector claim 1 , a dielectric mirror claim 1 , a multilayer dielectric mirror and a poly-electrolyte multilayer assembly.3. The probe as claimed in claim 1 , wherein said material of said radiation sensitive layer is a radiochromic material.4. The probe as claimed in claim 1 , further comprising a biocompatible sheath having a near water equivalent interaction with radiation claim 1 , said sheath covering said radiation sensitive layer claim 1 , said window and at least partly said optical fiber.5. The probe as claimed in claim 1 , further comprising an adhesive to assemble the window to the optical fiber provided with ...

HEAD AND NECK SIMULATION PHANTOM DEVICE

The present invention relates to a head and neck simulation phantom device for simulating the head and neck of a body, the phantom device including: a flat type first plate having a first insertion groove formed on one surface thereof; a flat type second plate disposed to come into contact with the other surface of the first plate and having a second insertion groove formed on the contacted surface with the other surface of the first plate in such a manner as to correspond to the first insertion groove; 1. A head and neck simulation phantom device for simulating the head and neck of a body , the phantom device comprising:a flat type first plate having a first insertion groove formed on one surface thereof;a flat type second plate disposed to come into contact with the other surface of the first plate and having a second insertion groove formed on the contacted surface with the other surface of the first plate in such a manner as to correspond to the first insertion groove; anda plurality of teeth simulants inserted into the first insertion groove and the second insertion groove and for simulating the teeth of the body.2. The head and neck simulation phantom device according to claim 1 , wherein the first plate and the second plate have through holes formed penetratedly thereinto.3. The head and neck simulation phantom device according to claim 1 , wherein each teeth simulant comprises: a cylindrical case; and an accommodated material located in the case.4. The head and neck simulation phantom device according to claim 3 , wherein the accommodated material comprises a titanium material or a tooth.5. The head and neck simulation phantom device according to claim 3 , wherein the case is made of a thermoplastic material.6. The head and neck simulation phantom device according to claim 1 , wherein the first plate and the second plate have dosimeter insertion grooves formed along the outer edges of the first insertion groove and the second insertion groove in such a ...

Real-Time X-Ray Dosimetry in Intraoperative Radiation Therapy

Real-time X-ray dosimetry sensing in intraoperative radiation therapy (IORT). According to one aspect, a treatment head comprises at least one X-ray component configured to facilitate generation of therapeutic radiation in the X-ray wavelength range. A resilient balloon is disposed over the treatment head and configured for receiving therein a fluid to facilitate X-ray treatment of a tumor cavity. A plurality of X-ray sensing elements is disposed at a plurality of locations distributed on the interior or exterior of the resilient balloon and configured for sensing X-ray radiation emanating from the treatment head. A control system is provided that is responsive to data received from the X-ray sensing elements to determine a magnitude of X-ray radiation detected at each of the X-ray sensing elements. 1. A method for real-time X-ray dosimetry , comprisingdisposing an X-ray treatment head within an inflatable balloon;inflating the balloon;using the X-ray treatment head to applying X-ray energy to a treatment surface external of the balloon; anddetecting an X-ray dose delivered by the treatment head to at least one location using at least one sensing element which is attached to a wall which forms a surface of the balloon.2. The method according to claim 1 , wherein the detecting step comprises detecting the X-ray dose delivered from the treatment head to a plurality of locations using a plurality of the sensing elements attached to a plurality of different locations on the wall of the balloon.3. The method according to claim 2 , wherein the plurality of different locations are respectively aligned with a plurality of points defined on the wall of the balloon where a plurality of orthogonal axes claim 2 , centered on the X-ray treatment head claim 2 , intersect the surface of the balloon claim 2 , when the balloon is inflated.4. The method according to claim 2 , wherein the plurality of different locations define an ovoid or spherical grid pattern on the surface of the ...

Stacked assembly of 2D radiochromic dosimeters to provide 3D dosimetric data

The invention relates to a polymeric dosimetric sheet with a thickness of 0.8 to 10.0 mm which contains a radiochromic dye and other additives and which reacts with x-ray or other ionizing radiation to form a stable color. The invention also relates to a stack of the dosimetric sheets which constitute a three-dimensional dosimeter. Upon irradiation, the sheet stack captures the radiation field of an applied radiation treatment plan. The irradiated sheet stack is disassembled and scanned with readily available devices to afford an array of two-dimensional images which can verify the treatment plan throughout the entire target volume by computerized methods. 1. A sheet dosimeter having a first face and a second face essentially parallel to said first face ,wherein each face has the same length and width, and a thickness; andwherein said length is between 10 and 25 cm and said width is between 1 and 25 cm, and said thickness is between 0.8 and 10.0 mm; andwherein said dosimeter is prepared from a formulation of a polyurethane prepolymer A, a polyurethane prepolymer B, a leuco dye, and additives selected from the group consisting of radical initiator, first solvent, second solvent, plasticizer, and softener; andwherein said sheet dosimeter is caused to have fiducial markings.2. A sheet dosimeter of wherein said formulation is introduced into a mold comprising a first endplate claim 1 , one or more spacers claim 1 , and a second endplate claim 1 , and said spacers are made to fit between the said endplates claim 1 , and said endplates and spacers are caused to be joined together claim 1 , said spacers causing a gap between said endplates claim 1 , said gap being between 0.8 to 10.0 mm claim 1 , said gap determining the thickness of the dosimeter; andwherein said formulation is allowed to cure within the mold held in essentially a vertical position at 20-30 degrees C. under 40-120 PSI pressure for between 8 hours and 7 days; andwherein the cured dosimeter is freed from ...

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 ...

Chromotropic Detection of Ionizing Radiation

A high contrast dosimeter is constructed where a plastic support is at least partially coated with a layer having a colored radical trapping compound. The plastic is a polymer that can contain a radiation sensitive plasticizer. The plastic forms radicals upon irradiation with high-energy (low wavelength) radiation. Upon diffusion of the radicals to the layer of radical trapping compound, reaction forms a compound with a different color than the radical trapping compound. In an embodiment of the invention, the plastic support is celluloid and the radical trapping compound is an azulenyl nitrone (AZN). 1. A high-energy radiation dosimeter , comprising:at least one plastic support comprising a polymer and, optionally, at least one plasticizer;an indicator layer comprising a radical trapping compound on at least a portion of the plastic support; andoptionally, a diffusion barrier covering the indicator layer distal to the plastic support, wherein the polymer and/or the radiation sensitive plasticizer forms a diffusible radical upon irradiation with electromagnetic radiation having a wavelength less than 10 nm.2. The high-energy radiation dosimeter of claim 1 , wherein the plastic support is celluloid.3. The high-energy radiation dosimeter of claim 1 , wherein the radical trapping compound is an azulenyl nitrons (AZN).5. The high-energy radiation dosimeter of claim 1 , where the diffusion barrier comprises a container claim 1 , coating or laminate layer.6. The high-energy radiation dosimeter of claim 1 , further comprising a filter layer wherein the filter layer blocks the transmission of UV radiation to the dosimeter.7. The high-energy radiation dosimeter of claim 1 , further comprising a contrast layer claim 1 , wherein the contrast layer resides on at least one portion of the plastic support other than the at least one portion having the layer comprising a radical trapping compound.8. The high-energy radiation dosimeter of claim 1 , wherein the polymer is radiation ...

APPARATUS AND METHODS FOR PERFORMING OPTICAL TOMOGRAPHY ON DOSIMETERS FOR CALIBRATING RADIOTHERAPY EQUIPMENT

An apparatus and method for performing tomography are disclosed herein. The apparatus includes an emitter for scanning an object with a detection beam, a diffuser for scattering a transmitted portion of the detection beam that passes through the object in order to generate a scattered signal, and at least one detector for detecting a portion of the scattered signal. The diffuser has a diffusive surface area, and the detector has a total detection area that is smaller than the diffusive surface area. 1. A method of calibrating radiotherapy equipment , the method comprising: (i) scanning the dosimeter by sweeping a detection beam across a plurality of segments of the dosimeter;', '(ii) scattering a transmitted portion of the detection beam that passes through the dosimeter to in order to generate a scattered signal, the scattered signal being generated by directing the transmitted portion across a diffuser having a diffusive surface area; and', '(iii) for each of the plurality of segments, detecting a portion of the scattered signal, the portion of the scattered signal being detected over a total detection area that is smaller than the diffusive surface area;, '(a) obtaining a reference image of a dosimeter using a tomography method comprising(b) after obtaining the reference image, irradiating the dosimeter with a test dosage of radiation from the radiotherapy equipment;(c) after irradiating the dosimeter with the test dosage, obtaining a calibration image of the dosimeter using the tomography method of step (a); and(d) comparing the reference image and the calibration image to model effects of the test dosage of radiation on the dosimeter.2. A method of performing tomography , the method comprising:(a) scanning an object with a detection beam;(b) scattering a transmitted portion of the detection beam that passes through the object in order to generate a scattered signal, the scattered signal being generated by directing the transmitted portion across a diffuser ...

OCULAR DOSIMETER AND MANUFACTURING METHOD THEREFOR

The present disclosure relates to a contact lens type dosimeter for measuring a dose distribution of a crystalline lens during radiation therapy, and a method of manufacturing the same. The ocular dosimeter has a contact lens shape and is configured to be worn on an eyeball, which comprises a basic material containing hydrophilic polyurethane, and a radiochromic dye. When the ocular dosimeter is worn on the eyeball, the dosimeter is configured to measure a radiation dose irradiated to a crystalline lens through a variation in color of the ocular dosimeter. 1. An ocular dosimeter having a contact lens shape and configured to be worn on an eyeball , the ocular dosimeter comprising:a basic material containing hydrophilic polyurethane; anda radiochromic dye,wherein, when the ocular dosimeter is worn on the eyeball, the ocular dosimeter is configured to measure a radiation dose irradiated to a crystalline lens through a variation in color of the ocular dosimeter.2. The ocular dosimeter of claim 1 , wherein the radiochromic dye comprises leucomalachite green (LMG).3. The ocular dosimeter of claim 1 , wherein the basic material containing hydrophilic polyurethane comprises hydroxyethyl methacrylate (HEMA) and CBr.4. A method of manufacturing ocular dosimeter claim 1 , comprising:preparing hydrophilic polyurethane in a first container;{'sub': '4', 'adding and dissolving CBrin the first container;'}adding and dissolving a radiochromic dye in the first container;preparing mixture liquid of hydrophilic polyurethane to which hydroxyethyl methacrylate (HEMA) is added in a second container different from the first container;mixing the mixture liquid of the first container with the mixture liquid of the second container and injecting a mixture of the mixture liquid of the first container and the mixture liquid of the second container into a female mold for a contact lens molding;covering the female mold with a male mold, molding the mixture in a form of a contact lens into, and ...

GAMMA-RAY MEASUREMENT DEVICE AND GAMMA-RAY MEASUREMENT METHOD

Provided are a gamma-ray measurement device and a gamma-ray measurement method which perform a gamma-ray measurement of simple and inexpensive structure in a mixed field of neutrons and gamma-rays. A gamma-ray measurement device is used in a method for measuring the dose in the same place when using a lead filter and when not using the filter, and obtaining a gamma dose from a difference. The gamma-ray measurement device includes a first detector which is made up of the lead filter for shielding gamma-rays and a glass dosimeter disposed in the center of the filter, and a second detector that is made up of only the glass dosimeter. 1. A gamma-ray measurement device comprising:a first detector which is disposed around a radiation dosimeter that is the same as a radiation dosimeter constituting a second detector used together, and is formed of lead or lead alloy, wherein the first detector is made up of a filter in which the thickness is determined such that an attenuation of neutrons and a correction factor of gamma-rays are within an allowable range in the measurement of gamma rays.2. The gamma-ray measurement device according to claim 1 , wherein the thickness of the filter is 2 cm or less and 1 cm or more in terms of pure lead.3. The gamma-ray measurement device according to claim 1 , wherein the filter further is a substantially hollow spherical body or a substantially cylindrical body having a uniform thickness in which a glass dosimeter is disposed in a center.4. The gamma-ray measurement device according to claim 3 , further comprising:a support member configured to support the glass dosimeter at a predetermined position therein.5. A gamma-ray measurement method comprising:{'claim-ref': {'@idref': 'CLM-00001', 'claim 1'}, 'placing the first detector of the gamma-ray measurement device according to , and the second detector made up of the same radiation dosimeter as the radiation dosimeter used in the first detector in a mixed field of neutrons and gamma-ray; ...

SYNTHETIC MATERIAL FOR DETECTING ULTRAVIOLET RADIATION AND/OR X-RADIATION

The invention relates to a material represented by the following formula (I) 124-. (canceled)25. A material represented by the following formula (I){'br': None, 'sub': 8', '6', '24', '2, '(M′)(M″M′″)O(X,S):M″″\u2003\u2003formula (I)'}whereinM′ represents a combination of at least two monoatomic cations of different alkali metals selected from a group consisting of Li, Na, K, and Rb;M″ represents a trivalent monoatomic cation of an element selected from Group 13 of the IUPAC periodic table of the elements, or of a transition element selected from any of Groups 3-12 of the IUPAC periodic table of the elements, or any combination of such cations;M′″ represents a monoatomic cation of an element selected from Group 14 of the IUPAC periodic table of the elements, or any combination of such cations;X represents an anion of an element selected from Group 16 of the IUPAC periodic table of the elements, or any combination of such anions, or X represents an anion of an element selected from a group consisting of F, Cl, Br, and I, or any combination of such anions; andM″″ represents a dopant cation of an element selected from rare earth metals of the IUPAC periodic table of the elements, or from transition metals of the IUPAC periodic table of the elements, or any combination of such cations, or wherein M″″ is absent.26. The material of claim 25 , wherein M′ represents a combination of at least two monoatomic cations of different alkali metals selected from a group consisting of Li claim 25 , Na claim 25 , K claim 25 , and Rb claim 25 , wherein the combination comprises 0-98 mol-% claim 25 , or 0-95 mol-% claim 25 , or 0-90 mol-% claim 25 , or 0-85 mol-% claim 25 , or 0-80 mol-% claim 25 , or 0-70 mol-% claim 25 , of the monoatomic cation of Na.27. The material of claim 25 , wherein M′ represents a combination of at least two monoatomic cations of different alkali metals selected from a group consisting of Li claim 25 , Na claim 25 , K claim 25 , and Rb claim 25 , and wherein ...

SYNTHETIC MATERIAL FOR DETECTING ULTRAVIOLET RADIATION AND/OR X-RADIATION

A material represented by the following formula (I) 1. A material represented by the following formula (I){'br': None, 'sub': 8', '6', '6', '24', '2, '(M′)M″M″′O(X,S):M″″\u2003\u2003formula (I)'}whereinM′ represents a combination of at least two monoatomic cations of different alkali metals selected from a group consisting of Li, Na, K, and Rb;M″ represents a trivalent monoatomic cation of an element selected from Group 13 of the IUPAC periodic table of the elements, or of a transition element selected from any of Groups 3-12 of the IUPAC periodic table of the elements, or any combination of such cations;M″′ represents a monoatomic cation of an element selected from Group 14 of the IUPAC periodic table of the elements, or any combination of such cations;X represents an anion of an element selected from Group 16 of the IUPAC periodic table of the elements, or any combination of such anions, or X represents an anion of an element selected from a group consisting of F, Cl, Br, and I, or any combination of such anions; andM″″ represents a dopant cation of an element selected from rare earth metals of the IUPAC periodic table of the elements, or from transition metals of the IUPAC periodic table of the elements, or any combination of such cations, or wherein M″″ is absent.2. The material of claim 1 , wherein M′ represents a combination of at least two monoatomic cations of different alkali metals selected from a group consisting of Li claim 1 , Na claim 1 , K claim 1 , and Rb claim 1 , wherein the combination comprises 0-98 mol-% claim 1 , or 0-95 mol-% claim 1 , or 0-90 mol-% claim 1 , or 0-85 mol-% claim 1 , or 0-80 mol-% claim 1 , or 0-70 mol-% claim 1 , of the monoatomic cation of Na.3. The material of claim 1 , wherein M′ represents a combination of at least two monoatomic cations of different alkali metals selected from a group consisting of Li claim 1 , Na claim 1 , K claim 1 , and Rb claim 1 , and wherein the combination comprises at most 66 mol-% of the ...

ENVIRONMENT DEPENDENT - TEMPERATURE INDEPENDENT COLOR CHANGING LABEL

A timing device comprises a sensing material and/or a component which is sensitive to the presence of an environmental attribute. The environmental attribute drives and speeds up or slows the timing device as the concentration of the attribute increases or decreases, respectively. Alternatively, the timing device is activated upon sensing the presence of the environmental attribute and indicates a total passage of time from exposure/activation of the timing device. Particularly, sensing materials of varying types are able to be used to indicate exposure to a variety of substances. For example, in some embodiments, the timing device comprises a sensing material which is sensitive to the presence of ultraviolet radiation. Alternatively, the sensing material is sensitive to other variables such as x-ray radiation and nuclear radiation. In further embodiments, the sensing material is sensitive to biological or physical contamination. 122-. (canceled)23. A timing device for indicating an exposure to an environmental attribute , comprising:a. one or more reactive zones, the one or more reactive zones configured to change color at a different time after being activated and being geometrically arranged to collectively indicate a total exposure to the environmental attribute,wherein the timing device is activated upon initial exposure to the environmental attribute.24. The timing device of claim 23 , wherein a portion of the reactive zones comprises a photosensitive medium that as developed changes color.25. The timing device of claim 23 , wherein a portion of the reactive zones comprise a diffusion layer and a dye that migrates through the diffusion layer to change color.26. The timing device of claim 23 , wherein a portion of the reactive zones comprises an electro-chemical material that is reduced or oxidized to change color.27. The timing device of claim 23 , wherein a rate of color change of the one or more reactive zones is directly related to a concentration of the ...

ENVIRONMENT DEPENDENT - TEMPERATURE INDEPENDENT COLOR CHANGING LABEL

A timing device comprises a sensing material and/or a component which is sensitive to the presence of an environmental attribute. The environmental attribute drives and speeds up or slows the timing device as the concentration of the attribute increases or decreases, respectively. Alternatively, the timing device is activated upon sensing the presence of the environmental attribute and indicates a total passage of time from exposure/activation of the timing device. Particularly, sensing materials of varying types are able to be used to indicate exposure to a variety of substances. For example, in some embodiments, the timing device comprises a sensing material which is sensitive to the presence of ultraviolet radiation. Alternatively, the sensing material is sensitive to other variables such as x-ray radiation and nuclear radiation. In further embodiments, the sensing material is sensitive to biological or physical contamination. 122-. (canceled)23. A timing device for indicating an exposure to an environmental attribute , comprising:a. one or more reactive zones, the one or more reactive zones configured to change color at a different time after being activated and being geometrically arranged to collectively indicate a total exposure to the environmental attribute, wherein the timing device is activated upon initial exposure to the environmental attribute.24. The timing device of claim 23 , wherein a portion of the reactive zones comprises a photosensitive medium that as developed changes color.25. The timing device of claim 23 , wherein a portion of the reactive zones comprise a diffusion layer and a dye that migrates through the diffusion layer to change color.26. The timing device of claim 23 , wherein a portion of the reactive zones comprises an electro-chemical material that is reduced or oxidized to change color.27. The timing device of claim 23 , wherein a rate of color change of the one or more reactive zones is directly related to a concentration of the ...

Colorimetric radiation dosimetry based on functional polymer and nanoparticle hybrid

A method for colorimetric radiation dosimetry includes subjecting an aggregate including a polymeric matrix having uniformly dispersed nanoparticles therein to radiation. The aggregate is soaked in a solution selected to dissolve decomposed pieces of the polymeric matrix to release into the solution nanoparticles from the decomposed pieces. Color of the solution is compared to a reference to determine a dose of radiation based on number of liberated nanoparticles.

COLORIMETRIC RADIATION DOSIMETRY BASED ON FUNCTIONAL POLYMER AND NANOPARTICLE HYBRID

A method for colorimetric radiation dosimetry includes subjecting an aggregate including a polymeric matrix having uniformly dispersed nanoparticles therein to radiation. The aggregate is soaked in a solution selected to dissolve decomposed pieces of the polymeric matrix to release into the solution nanoparticles from the decomposed pieces. Color of the solution is compared to a reference to determine a dose of radiation based on number of liberated nanoparticles. 1. A system for colorimetric radiation dosimetry , comprising:an aggregate including a polymeric matrix having uniformly dispersed nanoparticles therein to be subjected to radiation or a potential radiation source;a solution for soaking the aggregate being selected to dissolve decomposed pieces of the polymeric matrix to release into the solution nanoparticles from the decomposed pieces; anda color comparison device configured to measure color of the solution with liberated nanoparticles and compare the color to a reference to determine a dose of radiation based on number of the liberated nanoparticles.2. The system as recited in claim 1 , wherein the polymeric matrix includes at least one of polymethyl methacrylate and poly (olefin sulfones).3. The system as recited in claim 1 , wherein the color comparison device includes at least one of a spectrum analyzer for analyzing absorption spectra of the solution with the liberated nanoparticles and a color reference to determine radiation dose.4. The method as recited in claim 3 , wherein the nanoparticles include at least one of gold nanoparticles and quantum dots. This application is a Continuation application of co-pending U.S. patent application Ser. No. 13/868,654 filed on Apr. 23, 2013, incorporated herein by reference in its entirety.1. Technical FieldThe present invention relates to dosimetry, and more particularly to a composition, device and method for measuring radiation using change of color of a compound before and after exposure to radiation.2. ...

GAMMA RADIATION STAND-OFF DETECTION, TAMPER DETECTION, AND AUTHENTICATION VIA RESONANT META-MATERIAL STRUCTURES

Resonant meta-material structures are defined by metallic, dielectric or other materials that form nanoshells or nanomeshes that can be situated proximate to ionizing-radiation-sensitive layers so as to provide ionizing-radiation-dose-dependent optical properties. Such meta-material structures can also define aligned or periodic, semi-random, or other arrangements of nanostructures that are coupled to or include stressed layers. Detection of optical radiation from such structures is used to determine gamma radiation dose or to detect a disturbance of the nanostructure indicating tampering. 1. An apparatus , comprising:an ionizing-radiation-sensitive optical nanostructure;an optical radiation source that delivers an optical interrogation beam to the optical nanostructure; andan optical receiver that receives at least a portion of the optical interrogation beam from the optical nanostructure and provides an estimate of an ionizing-radiation dose based on the received portion.2. The apparatus of claim 1 , wherein the optical receiver is coupled to a display device that displays the estimated ionizing-radiation dose.3. The apparatus of claim 1 , wherein the ionizing-radiation-sensitive optical nanostructure comprises a plurality of oriented nanoshells.4. The apparatus of claim 3 , wherein the ionizing-radiation-sensitive optical nanostructure further comprises an ionizing-radiation-sensitive layer in contact with the plurality of oriented-nanoshells.5. The apparatus of claim 4 , wherein the plurality of oriented nanoshells is situated in the ionizing-radiation-sensitive layer.6. The apparatus of claim 3 , wherein the plurality of nanoshells is ionizing-radiation sensitive.7. The apparatus of claim 6 , wherein the nanoshells include at least one ionizing-radiation-sensitive shell layer.8. The apparatus of claim 1 , wherein the optical interrogation beam includes optical radiation at a plurality of wavelengths and the optical receiver provides the estimate of the ionizing ...

INTEGRATING RADIATION DOSIMETER

An implantable dosimeter uses salt crystals such as NaCl or KCl, or other materials that vary in color as a function of incident, ionizing radiation. The color change of the salts may occur through the creation of F-centers, where electrons become trapped in crystal defects (e.g., halide vacancies) and absorb light at certain wavelengths. Vacancies in the salt crystals absorb photons at precise wavelengths. Thus, the change in color can be correlated to the integrated dose in an implantation site. The salt crystals may be optically coupled to optical fibers or the like for remote measurement of color using, e.g., a spectrometer and a computer system. In this manner, the dosage of ionizing radiation can be measured in vivo with a fault tolerant, passively integrating dosimeter. 1. A system comprising:a unit of a material that exhibits a color change that varies as an integral of an amount of ionizing radiation incident on the unit;a casing about the unit of the material; andan optical coupling providing a terminal to optically couple an external device to the unit of the material.2. The system of wherein claim 1 , with the casing positioned in a patient claim 1 , the optical coupling is accessible external to the patient for optically coupling to the external device.3. The system of any one of - further comprising a fastener securable to a person to hold the casing in a relatively fixed position in proximity to the person.4. The system of wherein the fastener is securable to skin of the person.5. The system of any one of - wherein the fastener includes an adhesive.6. The system of any one of - wherein the fastener is securable to a garment wearable by the person.7. The system of wherein the fastener includes a clip.8. The system of any one of - further comprising:an illumination source optically coupled to the unit of the material through the optical coupling; andan optical sensor optically coupled to the unit of the material through the optical coupling.9. The ...

Colorimetric radiation dosimetry based on functional polymer and nanoparticle hybrid

A method for colorimetric radiation dosimetry includes subjecting an aggregate including a polymeric matrix having uniformly dispersed nanoparticles therein to radiation. The aggregate is soaked in a solution selected to dissolve decomposed pieces of the polymeric matrix to release into the solution nanoparticles from the decomposed pieces. Color of the solution is compared to a reference to determine a dose of radiation based on number of liberated nanoparticles.

Radiation dosimeter

A radiation dosimeter for measuring the dose of radiation applied during radiation therapy includes a substrate, a phosphor containing layer including a stimulable phosphor and a binder on a side of the substrate, the weight ratio of the binder to the phosphor in the phosphor containing layer is 10 or higher, a colorant, and optionally a layer in contact with the phosphor containing layer. The colorant provides a total light absorbance of the layers applied on the side of the substrate containing the phosphor containing layer of at least 0.04 at the stimulation wavelengths of the stimulable phosphor.

RADIATION MONITOR BASED ON WAVELENGTH-DEPENDENT OPTICAL ABSORPTION IN FUSED SILICA OPTICAL FIBERS

A radiation monitor apparatus and method based on wavelength-dependent optical absorption in fused silica optical fibers. The radiation monitor uses the radiation induced optical changes in fused silica optical fibers as a way to quantify and differentiate the large doses of radiation from high energy photons and neutrons as well as providing a method to extend the sensitivity over a large dynamic range of doses from 103 to beyond 106 rads. The radiation monitor enables dynamic monitoring of highly ionizing radiation environments. The radiation monitor reduces sensitivity saturation at high dose levels, provides increased sensitivity over a large dynamic range of doses, and enables differentiation between high energy photon and neutron contributions or poor signal to noise. 1. A method for remotely determining radiation dose caused by neutrons and high energy photons comprising:a photon source, a doped silica optical fiber, and a photon detector,transmitting light from the photon source through the optical fiber to the photon detector;measuring the intensity of the photons on the photon detector; anddetermining the optical attenuation changes to the optical fiber induced by the radiation as a function of time and temperature.2. The method of wherein said photon source comprises a broadband photon source.3. The method of wherein said broadband photon source comprises a diode laser.4. The method of wherein said broadband photon source is selected from the group consisting of ultraviolet photon source claim 2 , visible photon source claim 2 , and infrared photon source.5. The method of wherein the neutrons and high energy photons include gamma-rays and x-ray.6. The method of wherein said photon detector comprises a broadband photon detector.7. The method of wherein said doped silica fiber is selected from the group consisting of single mode fiber and multimode fiber.8. The method of comprising:said photon source outputs monochromatic light including a wavelength; ...

ALKALI FREE FLUOROPHOSPHATE BASED GLASS SYSTEMS

Alkali free fluorophosphate-based glass system that is highly radiation resistance (for example, they remain transparent and do not solarize before, during, and after application of high energy radiation of 10Rad or (1 kGy) or greater) and hence, reusable and further, when used with Ce provide a mechanism for determining the existence of radiation. 1. An alkali free fluorophosphate based glass system , comprising of:a glass base composition, having:{'sub': 3', '2, 'barium metaphosphate Ba(PO), in mol percent;'}{'sub': 3', '3, 'aluminum metaphosphate Al(PO)in mol percent, and'}one or more fluorides;where the one or more fluorides are selected from a group consisting of:{'sub': '2', 'barium fluoride BaFand RFx in mol percent;'}{'sub': 'x', 'where R is selected from a group consisting of: Mg, Ca, Sr, Pb, Y, Bi, Al, Zn, and combinations thereof, and subscript x is an index representing an amount of fluorine (F) in the compound RF;'}one or more dopant in wt % over 100 wt % of the glass base composition;{'sub': 3', '2', '3, 'where the one or more dopant is selected from a group consisting of: SbF, SbO, or combinations thereof; and'}{'sub': 2', '3', '2', '3', '3', '2', '3', '3', '2', '3', '3', '2', '3', '3', '2', '3', '3', '2', '3', '3', '2', '2', '3', '3', '2', '3', '3', '2', '3', '3', '2', '3', '3', '2', '3', '3', '2', '3', '3', '2', '2', '4', '2', '3', '3', '2', '3', '3', '2', '3', '3', '2', '4', '2', '3', '3', '2', '3', '3, 'one or more co-dopants in wt % over 100 wt % of the glass base composition selected from a group consisting of: CeO, CeF, ErO, ErF, NdO, NdF, YbO, YbF, PrO, PrF, EuO, EuF, TbO, TbF, ZnO, ZnF, HoO, HoF, SmO, SmF, TmO, TmF, LuO, LuF, GdO, GdF, DyO, DyF, CuO, CuF, TiO, TiF, CrO, CrF, MoO, MoF, WO, WF, MnO, MnF, CoO, CoF, NiO, NiF, and combinations thereof.'}2. An alkali free fluorophosphate based glass system , comprising of:a glass base composition, having:{'sub': 3', '2, 'barium metaphosphate Ba(PO), in mol percent,'}{'sub': 3', '3, 'aluminum ...

LUMINESCENT MATERIAL

The invention relates to a material represented by the following formula (I) 1. A material represented by the following formula (I){'br': None, 'sub': 8', '6', '24', '2, '(M′)(M′″M′″)O(X,X′):M″″'}formula (I)whereinM′ represents a monoatomic cation of an alkali metal selected from Group 1 of the IUPAC periodic table of the elements, or any combination of such cations;M″ represents a trivalent monoatomic cation of an element selected from Group 13 of the IUPAC periodic table of the elements, or of a transition element selected from any of Groups 3-12 of the IUPAC periodic table of the elements, or any combi-nation of such cations;M′″ represents a monoatomic cation of an element selected from Group 14 of the IUPAC periodic table of the elements, or of an element selected from any of Groups 13 and 15 of the IUPAC periodic table of the elements, or of Zn, or any combination of such cations;X represents an anion of an element selected from Group 17 of the IUPAC periodic table of the elements, or any combination of such anions, or wherein X is absent;X′ represents an anion of an element selected from Group 16 of the IUPAC periodic table of the elements, or any combination of such anions, or wherein X′ is absent; andM″″ represents a dopant cation of an element selected from transition metals of the IUPAC periodic table of the elements, or any combination of such cations;with the proviso that at least one of X and X′ is present.2. The material of claim 1 , wherein M′ represents a monoatomic cation of an alkali metal selected from Group 1 of the IUPAC periodic table of the elements claim 1 , or any combination of such cations claim 1 , with the proviso that M′ does not represent the monoatomic cation of Na alone.3. The material of claim 1 , wherein M′ represents a combination of at least two monoatomic cations of different alkali metals selected from Group 1 of the IUPAC periodic table of the elements.4. The material of claim 1 , wherein M′ represents a combination of at ...

Dosimeter for measuring neutron and gamma radiation

Glass Dosimeter Calibration Phantom for Quality Assurance

본 발명은 방사선 치료 시 환자의 신체에 유리선량계 또는 방사선감광 필름을 삽입하였을 경우를 모사하여 방사선량을 측정할 수 있는 정도관리를 위한 방사선량 측정용 팬텀에 관한 것으로, 본 발명에 따른 방사선량 측정용 팬텀은 중앙부에 카트리지삽입홀이 형성되어 있는 본체와; 상기 본체의 카트리지삽입홀과 대응하는 형태로 되어 카트리지삽입홀 내측으로 삽입되며, 일단부에 카트리지장착부가 돌출되게 형성되어 있는 제1마운트부재와; 상기 제1마운트부재의 카트리지장착부에 끼워져 결합되며, 원통형으로 된 유리선량계가 삽입되는 선량계삽입홀이 관통되게 형성되어 있는 링형태의 카트리지와; 일단부에 상기 제1마운트부재의 카트리지장착부의 끝단부가 형합되는 결합홈부가 오목하게 형성되어 상기 제1마운트부재의 일단부에 결합되면서 카트리지를 지지하며, 상기 본체의 카트리지삽입홀과 대응하는 형태로 이루어져 상기 제1마운트부재 및 카트리지와 함께 상기 본체의 카트리지삽입홀 내측으로 삽입되는 제2마운트부재를 포함하는 것을 특징으로 한다. The present invention relates to a radiation dose measurement phantom for quality control that can measure the radiation dose by simulating the case of inserting a glass dosimeter or radiation photosensitive film into the body of the patient during radiation treatment, the radiation dose measurement according to the present invention The phantom includes: a main body in which a cartridge insertion hole is formed in the center portion; A first mounting member which has a shape corresponding to the cartridge insertion hole of the main body, is inserted into the cartridge insertion hole, and has a cartridge mounting portion protruding at one end thereof; A ring-shaped cartridge inserted into and coupled to the cartridge mounting portion of the first mount member and configured to penetrate a dosimeter insertion hole into which a cylindrical glass dosimeter is inserted; A coupling groove portion formed at one end of the cartridge mounting portion of the first mounting member is formed in a concave shape to support the cartridge while being coupled to one end of the first mounting member and to correspond to the cartridge insertion hole of the main body. And a second mount member inserted into the cartridge insertion hole of the main body together with the first mount member and the cartridge.

Radiation dose indicator

Method and apparatus for measuring glass dose

(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。

Tamper resistant self indicating instant alert radiation dosimeter

A tamper resistant and evident, self indicating instant radiation alert dosimeter (referred to as SIRAD) made by encapsulating a radiation sensing system in a polymeric material is disclosed. SIRAD is made from many layers of polymeric materials by multi-step processes. The radiation sensing system of SIRAD is encapsulated in a polymeric media made by a casting or reaction injection molding process.

Real-time x-ray dosimetry in intraoperative radiation therapy

Real-time X-ray dosimetry sensing in intraoperative radiation therapy (IORT). According to one aspect, a treatment head comprises at least one X-ray component configured to facilitate generation of therapeutic radiation in the X-ray wavelength range. A resilient balloon is disposed over the treatment head and configured for receiving therein a fluid to facilitate X-ray treatment of a tumor cavity. A plurality of X-ray sensing elements is disposed at a plurality of locations distributed on the interior or exterior of the resilient balloon and configured for sensing X-ray radiation emanating from the treatment head. A control system is provided that is responsive to data received from the X-ray sensing elements to determine a magnitude of X-ray radiation detected at each of the X-ray sensing elements.

General purpose, high accuracy dosimeter reader

A general purpose high accuracy dosimeter reader, 80 , for determination of a treatment condition, based on comparison of an image of treated dosimeter, 111 , with a series of images of pre-treated dosimeter, 114 , is disclosed. A dosimeter undergoes noticeable changes, such as a color change upon treatment with certain materials, such as toxic gases and processes, such as ionizing radiation and sterilization is pre-treated. The dosimeter is imaged with an imaging device, 115 , such as charge-coupled device camera and images of the dosimeter or the changes, e.g., color change, are stored in an information storage device, 118 . In order to determine the treatment condition, the treatment dosimeter is imaged and the image is compared with the series of pre-treated images of the dosimeter using software. The closest match of the treated dosimeter with the pre-treated and pre-imaged dosimeter would indicate the treatment conditions. The process and device can be used for almost any indicating device, process and treatment.

Self indicating radiation alert dosimeter

Described is a self-indicating instant radiation dosimeter ( 1001 ) for monitoring high energy radiations, such as X-ray. The dosimeter contains a radiation sensitive, color changing, indicating composition ( 10 ), e.g., a diacetylene (R—C≡C—C≡C—R′, where R and R′ are substituents groups) or a radiochromic dye, a polymeric binder ( 20 ) and optionally a shelf life extender ( 50 ) or an activator ( 40 ). The radiation sensitive composition ( 10 ) changes color instantly when exposed to high energy radiation. The dose is estimated by comparing the color with a color reference chart or more accurately with a spectrophotometer or an optical densitometer. The radiation sensitive composition ( 10 ) is protected from low energy radiation such as UV light, by a layer of low energy absorbing materials, such as UV absorbers.

Perovskite quantum dot scintillation glass-ceramic and preparation method thereof

本发明公开了一种钙钛矿量子点闪烁微晶玻璃及制备方法，闪烁微晶玻璃以CsPbBr3量子点为发光中心，以碲酸盐玻璃作为包覆基质，所述闪烁微晶玻璃的玻璃基质的原料摩尔组成为：TeO 2 ：50‑95％；M 2 O 3 ：1‑20％，M＝B、Al、Ga或In；ZnO：0‑20％；CsBr：1‑15％；PbBr2：1‑15％；在玻璃基质中掺入Ag + 作为晶核剂，Ag + 的掺杂浓度摩尔比为0.1‑1％。本发明制备工艺简单，易实现大尺寸制备，可重复性高，化学组分可调，熔融温度低，具有优异的光稳定性，更高的玻璃密度和折射率，优良的高能射线截止能力，有助于实现高信噪比辐射探测，可用于X光剂量计等闪烁发光器件。

Radiation monitoring apparatus and manufacturing method thereof

High resolution imaging using optically transparent phosphors

(57)【要約】 発光中心と捕獲中心を含む、光学的に透明で光学的に励起されうるガラス（４２）をパターン化された電離放射線源に露出することにより、影像を生成する。影像は、シンチレーションを使って即時に読み取るか、ガラスに保存して、後で保存された捕獲電荷を光学的な励起により（１４）リリースし、読み取るようにしてもよい。

A radiation detection material and the method of detection using thereby

본 발명은 아밀로오스 분자 및 아이오다이드 이온을 포함하는 염을 포함하는 방사선 검출 물질을 제공한다. 본 발명에 따른 방사선 검출 물질은 중성자, 감마선, 베타선, 전자선 및 자외선 등의 방사선에 조사되었던 여부를 쉽게 파악할 수 있다. 또한, 환원제의 양을 조절하여 복수의 방사선 검출 물질군을 사용하면 조사된 방사선의 세기도 가늠할 수 있다. 이와 같이 방사선 피폭 여부를 쉽게 파악할 수 있는 효과가 있다. The present invention provides a radiation detection material comprising a salt comprising an amylose molecule and an iodide ion. The radiation detecting material according to the present invention can easily detect whether it is irradiated with radiation such as neutrons, gamma rays, beta rays, electron beams and ultraviolet rays. In addition, the intensity of the irradiated radiation can be measured by using a plurality of groups of the radiation detecting substances by adjusting the amount of the reducing agent. Thus, it is possible to easily grasp whether or not the radiation is exposed.

Glasses for measuring radiation doses

Head and neck phantom device

The present invention relates to a phantom device for mimicking the head and neck of a human body in which radioactivity can be measured instead of the human body, and which can assess dose error generated by teeth, implant, etc. existing in the human body. According to an embodiment of the present invention, the phantom device comprises: a planar first plate in which a first insertion groove is formed on one surface; a planar second plate which is disposed to be in contact with the one surface of the first plate, and in which a second insertion groove corresponding to the first insertion groove is formed on a contact surface being in contact with the one surface; and a plurality of tooth mimics which are inserted into the first and second insertion grooves, and mimic teeth of the human body.

Radiation intensity measuring device

Radiation detecting elements and method of detection

Radiation detecting solid elements consisting of conductive polymers and radiation sensitive materials which are capable of generating radiation induced substances composing the dopant of the conductive polymers. The elements are monolayer sheets obtained by impregnating or compounding the conductive polymers, such as, polythiophene and polyselenophene, with radiation sensitive materials, such as, diphenyliodonium chloride and triphenylsulfonium hexafluoroarsenate(V). The elements are also laminated sheets consisting of conductive polymer films and radiation sensitive material containing films. As radiation exposure causes variation in electrical conductivity and absorption spectrum of the elements, radiation can be detected by the variation of these properties.

High resolution imaging using optically transparent phosphors

Images are formed by exposing optically transparent, optically stimulable luminescent glasses including luminescent centers and trapping centers, to patterned, ionizing radiation. The images may be read immediately, using scintillation, or may be stored in the glasses for subsequent reading using optically stimulated detrapping of stored charges.

Glass for radiation detection

Provided is a glass for radiation detection having high fluorescence detection sensitivity and high weather resistance. The glass for radiation detection is characterized by containing, in mol%, 0.1-30% of SiO 2 +B 2 O 3 , 0-20% of SiO 2 , 0-10% of B 2 O 3 , 40-70% of P 2 O 5 , 10-30% of Al 2 O 3 , 10-30% of Na 2 O, and 0.01-2% of Ag 2 O.

Radiation monitor based on wavelength-dependent optical absorption in fused silica optical fibers

A radiation monitor apparatus and method based on wavelength-dependent optical absorption in fused silica optical fibers. The radiation monitor uses the radiation induced optical changes in fused silica optical fibers as a way to quantify and differentiate the large doses of radiation from high energy photons and neutrons as well as providing a method to extend the sensitivity over a large dynamic range of doses from 103 to beyond 106 rads. The radiation monitor enables dynamic monitoring of highly ionizing radiation environments. The radiation monitor reduces sensitivity saturation at high dose levels, provides increased sensitivity over a large dynamic range of doses, and enables differentiation between high energy photon and neutron contributions or poor signal to noise.

Radiation dosimeter

一种用于测量在辐射疗法期间应用的辐射的剂量的辐射剂量计，包括：衬底；磷包含层，包括所述衬底的侧上的粘合剂和可刺激磷，所述磷包含层中粘合剂与磷的重量比是10或更高；着色剂；以及可选地，与所述磷包含层接触的层，所述着色剂提供在所述衬底的包含所述磷包含层的侧上应用的层的总光吸收度，其在所述可刺激磷的刺激波长处为至少0.04。

High resolution imaging using optically transparent phosphors

Monitoring apparatus for measuring dose of brachytherapy radiation

The apparatus for inspecting a near-field radiation dose according to the present invention includes a dose unit including at least one dose plate provided with a dose meter for measuring a dose of radiation, and at least one photosensitive plate provided with a photoconductor for measuring a dose of radiation dose And a phantom unit into which a radiation source for inserting the radiation dose unit and the photosensitive unit is inserted. According to this configuration, the radiation dose can be inspected from the outside or remotely, thereby contributing to the improvement of the high-precision dose evaluation quality.

Gamma ray measurement apparatus and gamma ray measurement method

Synthetic materials for detecting ultraviolet and/or X-ray radiation

본 발명은 하기의 화학식 (I)로 표현되는 물질에 관한 것이다. [화학식 I] (M') 8 (M''M''') 6 O 24 (X,S) 2 :M'''' 또한, 본 발명은 자외선 방사 감지 물질, X-선 방사 감지 물질, 상이한 용도, 자외선 방사의 강도를 결정하는 장치 및 방법에 관한 것이다. The present invention relates to a substance represented by the following formula (I). [Formula I] (M') 8 (M''M''') 6 O 24 (X,S) 2 :M'''' The invention also relates to ultraviolet radiation sensing materials, X-ray radiation sensing materials, different uses, devices and methods for determining the intensity of ultraviolet radiation.

Multiple medical patches on a single strip and a process for manufacturing thereof

An article of manufacture for use in removing corns and callus from a person comprising a first strip comprising a backing member and first and second medicated patches having salicylic acid releaseably affixed to the backing member. Each of the first and second mediated patches comprise first and second outside edges and an inside edge. The first and second medicated patches are nested and adjoined along the inside edges of said first and second medicated patches, respectively.

Radiation Indicator

본 발명은 보다 높은 에너지를 갖는 방사선이 조사되었을 때 발색하고, UV 등 주변광을 차폐하여 장기간 충분한 품질을 유지할 수 있는 방사선 지시기를 제공하는 데 있다. 이를 위하여 본 발명은 높은 에너지를 갖는 전리 방사선이 조사되었을 때에 검출 가능한 색 변화를 발색하는 성능을 갖는 라디오 크로믹 재료; 및 금속 산화물을 포함할 수 있다. 본 발명에 방사선 지시기는 주변광 등의 통상의 주위 조건에는 수개월 사이 및 태양광에는 몇 일간 영향을 받지 않을 수 있어 충분한 품질 보유 기간을 가질 수 있다. 또한 본 발명에 따른 방사선 지시기는 에멀젼 상태로 금속 산화물이 포함된 라디오 크로믹 재료로부터 제조될 수 있어, 다양한 로고 및 지시서가 결합이 가능하고, 평면, 사각형, 직사각형, 삼각형, 육각형을 포함한 다양한 형상 및 위치에 제작될 수 있다.

Stable radiochromic dosimetry film and manufacturing method thereof

低エネルギーのＸ線に感受性のあるフィルム媒体であり、該フィルム媒体は、患者の皮膚障害を引き起こすおそれがある範囲である約200から約1500ラッドまでの範囲内の照射線量を測定するために使用するのに適している。または、本発明のフィルム製造物は、大きいシートの状態で作製することができる。従って、照射線量の最大地点の位置を必ずしも知っているわけではない場合に、外科手術中に使用するのに、特に体全体を照射するのに適している。本発明のフィルム媒体は、低エネルギーのＸ線を透過させることができる重合体フィルムの第１の支持層と、十分に結晶質であって、画像を受容するポリアセチレン化合物の微晶性分散体と、入射する低エネルギーの光子放射線を選択的に吸収する化合物を含む組成物であり、該第１の層の上にある第２の層とからなる。

Fluorescent glass dosimeter

(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。

SYNTHETIC MATERIAL FOR DETECTING ULTRAVIOLE RADIATION AND / OR X-RAY RADIATION

Apparatus for measuring radiation dose

An apparatus for measuring radiation dose using the change in light absorbance of a transparent material upon irradiation which comprises substantially a light source, a monochromatic light emitting unit, a unit for controlling the light amount, a sample mounting unit, a detection unit and an indication unit wherein said light source is a hollow cathode lamp is herein disclosed.

Nuclear radiation measuring apparatus and method

A visually readable nuclear radiation measurement device functioning as a dose rate meter or a dosimeter. There are disclosed several embodiments allowing the user to match the brightness of a scintillating means (1) to a reference light source (2) thereby to ascertain the desired dose rate radiation information and allowing the user to match the brightness of light penetrating a dye type dosimeter to a reference light source (2) to ascertain the total dose.

Calibration Phantom for Brachytherapy Radiation

The present invention relates to a phantom for measuring a dose of brachytherapy radiation which is used in measuring radiation dose to manage a degree of a brachytherapy radiation treatment. According to the present invention, the phantom for measuring a dose of brachytherapy radiation includes a base plate formed of a synthetic resin material in the shape of a flat plate, and having a cut groove formed on one side and a tube insertion hole formed to be extended in one direction from the inner side of the cut groove; a metallic tube installed by being inserted into the tube insertion hole of the base plate, and in which an end portion is protruding to the inside of the cut groove so that a radioactive source can be inserted through the end portion; and a tube cap detachably coupled to the cut groove to cover the cut groove, and having a tube protection hole into which the end portion of the tube protruding to the inside of the cut groove is inserted.

Synthetic material for detecting ultraviolet radiation and/or X-radiation

The invention relates to a material represented by the following formula (I) (M′) 8 M″ 6 M′″ 6 O 24 (X,S) 2 :M″″  formula (I). Further, the invention relates to an ultraviolet radiation sensing material, to an X-radiation sensing material, to different uses, to a device and to a method for determining the intensity of ultraviolet radiation.

High temperature dosimeter

Dosimeter housing

A dosimeter housing includes an upper case 10 and a lower case 20, housing a glass element 1 for measuring a radiation dose, and being openable and closable. Elastic bodies 80a to 80d are provided in the upper case 10, and attaches the lower case 20 to the upper case 10. The attachment of the upper case 10 and the lower case 20 by the elastic bodies 80a to 80d is released by an insertion of an opening jig 98 inserted into jig insertion openings 21a to 21d provided in the lower case 20.

Phantom apparatus for measuring dose of brachytherapy radiation

The phantom device for measuring a near-field radiation dose according to the present invention includes a base plate provided with a plurality of installation grooves on which a plurality of dose meters are installed, a cover plate provided with a plurality of cover grooves covering the plurality of dose meters, And a photosensitive plate which is laminated on the base plate with the cover plate therebetween and in which the radiation photosensitive member is embedded. According to this configuration, it becomes possible to acquire a radiation dose distribution in addition to the radiation dose measurement, thereby contributing to the improvement of the treatment precision according to the improvement in the prediction accuracy of the radiation dose to be irradiated to the patient during treatment.

Evaluation procedure for glass dosimeters

Optical fiber grating based dosimeter and system to monitor dose having the same

본 발명의 실시예에 따른 광섬유 격자 기반 방사선량계는, 방사선 조사에 의해 광섬유 격자의 공진파장 이동을 관측하여 방사선량을 측정하는 광섬유 격자 기반 방사선량계로서, 광섬유에 구조적 변화를 발생시킴으로써 광섬유에 주기적인 격자 패턴을 형성하고 격자 패턴을 통해 주기적인 굴절률 변화가 발생되는 광섬유 격자를 포함할 수 있다. 본 발명의 실시예에 따르면, 광섬유에 있어서 광민감성을 요구하지 않기 때문에 광섬유 종류에 무관하게 제작이 가능하여 낮은 비용, 높은 생산성을 가질 수 있으며 또한 광섬유 선택에 따라 측정 범위를 용이하게 조절할 수 있다. An optical fiber grating based dosimeter according to an embodiment of the present invention is an optical fiber grating based dosimeter which measures the radiation dose by observing the resonant wavelength movement of the optical fiber grating by irradiation, and generates periodic structural changes in the optical fiber. It may include an optical fiber grating to form a grating pattern and a periodic refractive index change through the grating pattern. According to the embodiment of the present invention, since optical sensitivity is not required in the optical fiber, the optical fiber can be manufactured regardless of the optical fiber type, so that the optical fiber can have low cost and high productivity, and the measurement range can be easily adjusted according to the optical fiber selection.

SYNTHETIC MATERIAL FOR DETECTING ULTRAVIOLET RADIATION AND/OR X-RAY RADIATION

Synthetic material for detecting ultraviolet light

Real-time X-ray dosimetry in intraoperative radiation therapy

术中放射治疗(IORT)中的实时X射线剂量测定感测。根据一个方面，一种治疗头包括至少一个X射线组件，该至少一个X射线组件被配置为有助于生成在X射线波长范围内的治疗放射。弹性球囊布置在治疗头上方，并且被配置成用于在其中容纳流体以有助于对肿瘤腔的X射线治疗。多个X射线感测元件布置在分布于弹性球囊的内部或外部的多个位置处，并且被配置成用于感测从治疗头发出的X射线放射。提供一种控制系统，其响应于从X射线感测元件接收的数据以确定在每个X射线感测元件处检测到的X射线放射的大小。

PROCEDURE FOR PREPARING A GLASS FOR DOSIMETRY OF RAYS WITH WAVE LENGTHS BELOW 100 DEGREES , AND OBJECTS MOLDED THEREOF.

ANALYTICAL MATERIAL FOR DOSIMETRY OF IONIZING RADIATION

Der bisherige Nachteil bei der Anwendung von Elektronenbeschleunigungsanlagen zum Bestrahlen der unterschiedlichsten Produkte, die nur in unzureichender Qualitaet oder nicht vorhandene Dosimetrie zur Analyse, Steuerung und Ueberwachung dieser Anlagen, wird durch den Einsatz neuer analytischer Materialien beseitigt. Diese Materialien bedienen sich zur Analyse der Strahlungsfelder Polyethylenterephthalatfolien, deren Auswertung ueber Transmissionswertdifferenzen erfolgt. Die im Bereich von 0-2 500 kGy verwendbaren Folien sind durch folgende Parameter charakterisiert:Dichteg/cm31,3931,397Dickemm 951ZugfestigkeitN/mm2 20010Dehnung% 10010Kristallinitaet% 551,5Thermoschrumpfung% % The previous disadvantage in the application of electron acceleration systems for irradiating a wide variety of products, the only inadequate quality or nonexistent dosimetry for analysis, control and monitoring of these systems, is eliminated by the use of new analytical materials. For the analysis of the radiation fields, these materials use polyethylene terephthalate films, the evaluation of which takes place via transmittance value differences. The films usable in the range of 0-2 500 kGy are characterized by the following parameters: density / cm31.3931.397Dickemm 951 tensile strengthN / mm2 20010 elongation% 10010crystallinity% 551.5Thermo shrinkage%%

Radiation dosimeter

A radiation dosimeter for preparing a dosage map of a specific rotary canister of a blood radiating machine. This dosimeter (14) includes a sandwich assembly of a first panel (16) and a second panel (18) and a gamma ray-sensitive film (20) disposed there- between, for mounting temporarily in the canister (12) during gamma ray dosage and canister rotation.

Synthetic material for detecting ultraviolet radiation

【課題】紫外線の強度を測定するための、材料、紫外線検知材料、デバイス、該材料の使用、及び方法の提供 【解決手段】（Ｍ’） ８ （Ｍ’’Ｍ’’’） ６ Ｏ ２４ （Ｘ，Ｓ） ２ ：Ｍ’’’’によって表される材料。（Ｍ’は１族から選択された異なるアルカリ金属の少なくとも２つの単原子カチオンの組合せ；Ｍ’’は１３族から選択された元素、又は３〜１２族のいずれかから選択された遷移元素の３価単原子カチオン、或はそれらカチオンの任意の組合せ；Ｍ’’’は１４族から選択された元素の単原子カチオン、又はそれらカチオンの任意の組合せ；Ｘは１６族から選択された元素のアニオン、或はＦ、Ｃｌ、Ｂｒ、及びＩから選択された元素のアニオン、又はそれらアニオンの任意の組合せ；Ｍ’’’’は希土類金属から若しくは遷移金属から選択された元素のドーパントカチオン、又はそれらカチオンの任意の組合せ） 【選択図】図１

Fibre-optic sensor for tissue-equivalent radiation dosimetry

A sensor for measuring a tissue equivalent radiation dose has a radiation-sensitive optical fibre (4), means (1, 3) for coupling and outcoupling light in and out of the radiation-sensitive optical fibre (4) and a reflecting coating (2) on both ends of the radiation-sensitive optical fibre (4). Light fed into the radiation-sensitive optical fibre (4) is reflected back and forth several times, lengthening the path of the light over conventional sensors. The lengthened path of the light leads to an improved sensitivity without affecting spatial resolution.

Dosimeter to manufacture optical fiber for filling high molecular compound

본 발명의 실시예에 따른 고분자 화합물이 충진된 광섬유 기반 방사선량계는, 광섬유의 내부에 방사선 감응성 고분자 화합물을 주입함으로써, 방사선 감응성 고분자 화합물의 광 특성 변화에 의해 광섬유에 조사된 방사선의 굴절률을 증가시키며 이를 통해 방사선의 투과파장의 이동을 관측하여 방사선량을 측정하는 광섬유 방사선 센서부를 포함할 수 있다. 본 발명의 실시예에 따르면, 광원에 대해서 광섬유에 구비되는 방사선 감응성 고분자 화합물의 투과 특성을 이용하기 때문에 분해능이 높으면서도 전자기장의 간섭을 받지 않음으로써 방사선량 측정의 정확성을 높일 수 있다. The optical fiber-based radiation dosimeter filled with the polymer compound according to the embodiment of the present invention increases the refractive index of the radiation irradiated onto the optical fiber by changing the optical properties of the radiation-sensitive polymer compound by injecting the radiation-sensitive polymer compound into the optical fiber. This may include an optical fiber radiation sensor unit for measuring the radiation dose by observing the movement of the transmission wavelength of the radiation. According to an embodiment of the present invention, since the transmission characteristics of the radiation-sensitive polymer compound provided in the optical fiber are used for the light source, the radiation dose can be increased and the accuracy of the radiation dose measurement can be improved by being free from interference of the electromagnetic field.

Tamper resistant self indicating instant alert radiation dosimeter

A tamper resistant and evident, self indicating instant radiation alert dosimeter (referred to as SIRAD) made by encapsulating a radiation sensing system in a polymeric material is disclosed. SIRAD is made from many layers of polymeric materials by multi-step processes. The radiation sensing system of SIRAD is encapsulated in a polymeric media made by a casting or reaction injection molding process.

Controlled defect coloration dosimeter

High-symmetry organic scintillator systems

An ionizing radiation detector or scintillator system includes a scintillating material comprising an organic crystalline compound selected to generate photons in response to the passage of ionizing radiation. The organic compound has a crystalline symmetry of higher order than monoclinic, for example an orthorhombic, trigonal, tetragonal, hexagonal, or cubic symmetry. A photodetector is optically coupled to the scintillating material, and configured to generate electronic signals having pulse shapes based on the photons generated in the scintillating material. A discriminator is coupled to the photon detector, and configured to discriminate between neutrons and gamma rays in the ionizing radiation based on the pulse shapes of the output signals.

Dosimeter for the detection of radiation using radio-photo-luminescence

Luminescent material

Direct skin radiation dose measurement system with quantitative optical read-out

General purpose, wide energy range calibration source for medical emission tomography

For calibration in medical emission tomography, the dosimeter and/or detector is calibrated in the field, such as at the clinic or other patient scanning location. To allow for a fewer number of calibration sources used in calibrating and/or assist in calibration for multispectral emission tomography, a calibration source includes multiple isotopes and/or a proxy source or isotope is used instead of the same isotope used in factory calibration.

Novel radiation detector

The invention provides a device for the detection and mapping of radiation, the device comprising a polymeric core located within an external shell material, wherein the polymeric core comprises at least one radiation sensitive component and the external sheath comprises a collimation sheath. Preferably, the polymeric core comprises a spherical core which is encased within the external shell. The external shell is preferably comprised of a metal, most preferably lead or tungsten. The invention also provides a method for the detection and mapping of radiation in a location, which comprises: (a) placing a device according to the invention in the location to be investigated; (b) allowing the device to remain in the location and be exposed to the radiation for a predetermined length of time; (c) removing the device from the location; (d) removing the polymeric core from the external shell; and (e) analysing said polymeric core by means of an optical analysis technique applying a software-based image reconstruction algorithm in order to determine the location, form and intensity of said radiation. The device and method of the invention facilitate the detection and mapping of radiation, and find particular use in mapping the location, intensity and identity of radio-logical hazards in 3 dimensions in sites such as active cells, gloveboxes, other active plants and confined spaces. Advantages over the prior art include the lack of requirement for an electrical supply, and the ability to deal with high radiation backgrounds and to be deployed in confined or restricted spaces.