Charge transport tactical dosimeter
    1.
    发明授权
    Charge transport tactical dosimeter 失效
    电荷运输战术剂量计

    公开(公告)号:US4019058A

    公开(公告)日:1977-04-19

    申请号:US625341

    申请日:1975-10-23

    IPC分类号: G01T1/14 G01T1/18

    CPC分类号: G01T1/14

    摘要: A quartz fiber electroscope shunted by a variable capacitor is periodically coupled to a radiation detection capacitor formed of material of a relatively large atomic number, e.g. aluminum, completely surrounded by a material of lesser atomic number, e.g. polyethylene. An electrical charge is induced by neutron or gamma radiation on the material of relatively large atomic number which charge is then coupled to the electroscope and variable capacitor combination. The variable capacitor is set at its maximum when the voltage is transferred from the detection capacitor. The variable capacitor is then reduced, thus raising the voltage on the electroscope with the dose being determined by the reduction in capacitance necessary to raise the indicated electrometer voltage to a predetermined magnitude. The variable capacitor includes indicia thereon which is calibrated such that the voltage change provides a direct reading of the charge transfer and consequently dosage.

    摘要翻译: 由可变电容器分流的石英光纤监视器周期性地耦合到由较大原子数的材料形成的放射线检测电容器,例如, 铝,完全被原子序数较少的材料包围 聚乙烯 中子或伽马辐射在相对较大原子序号的材料上引起电荷,然后将该电荷耦合到电镜和可变电容器组合。 当电压从检测电容器转移时,可变电容器设置为最大值。 然后可变电容器被减小,从而提高电镜上的电压,其剂量由通过将指示的静电计电压升高到预定大小所需的电容的减小来确定。 可变电容器包括其上的标记,其被校准为使得电压变化提供电荷转移的直接读数并因此提供剂量。

    Solid state nuclear radiation detector circuit with constant sensitivity
    2.
    发明授权
    Solid state nuclear radiation detector circuit with constant sensitivity 失效
    固态核辐射检测电路,灵敏度不变

    公开(公告)号:US4527063A

    公开(公告)日:1985-07-02

    申请号:US576992

    申请日:1984-02-06

    IPC分类号: G01T1/17 G01T1/24

    CPC分类号: G01T1/17

    摘要: This circuit comprises a solid state crystal radiation counter having its plified output connected in parallel to a pair of pulse height discriminators with thresholds of V.sub.1 and 2V.sub.1 volts, wherein V.sub.1 is above the counter noise level. A pair of pulse counters are arranged to count the outputs of the discriminators and a processor circuit is connected to the pulse counter outputs and is arranged to calculate the quotient of the square of the output of the pulse counter connected to the discriminator with the lower threshold and the output of the other pulse counter. A display circuit is arranged to provide a reading related to the output of the processor circuit.

    摘要翻译: 该电路包括固态晶体辐射计数器,其具有与具有V1和2V1伏特的阈值的一对脉冲高度鉴别器并联连接的放大输出,其中V1高于反噪声电平。 一对脉冲计数器被布置成对鉴别器的输出进行计数,并且处理器电路连接到脉冲计数器输出,并且被布置为计算连接到鉴别器的脉冲计数器的输出的平方值与下阈值 和另一个脉冲计数器的输出。 显示电路被布置成提供与处理器电路的输出有关的读取。

    Dodecahedron neutron spectrometer with aluminum proton absorber for aircraft
    3.
    发明授权
    Dodecahedron neutron spectrometer with aluminum proton absorber for aircraft 失效
    具有铝质子吸收器的十二面体中子谱仪用于飞机

    公开(公告)号:US06625243B1

    公开(公告)日:2003-09-23

    申请号:US10229201

    申请日:2002-08-27

    IPC分类号: G21H100

    CPC分类号: G01T3/08

    摘要: A neutron spectrometer for aircraft is provided by a series of substrates covered by a solid-state detector stacked on an absorbing layer. As many as 12 substrates that convert neutrons to protons are covered by a layer of absorbing material, acting as a proton absorber, with the detector placed within the layer to count protons passing through the absorbing layer. By using 12 detectors the range of neutron energies are covered. The preferred dodecahedron embodiment of the neutron spectrometer is a solid, polyethylene dodecahedron assembly with 12 surface facets covered by a solid-state detector stacked on an absorbing layer composed of aluminum. Each absorbing layer is constructed with a different thickness according to the minimum and maximum energies of neutrons in the spectrum. In this arrangement, each of the 12 surface pentagon-shaped facets provides a polyethylene substrate to convert neutrons to protons, covered by a layer of absorbing material, acting as a proton absorber, with the detector stacked on the absorbing layer to count protons passing through the absorbing layer. The dodecahedron assembly is housed concentrically within a titanium spherical shell that serves as an outer shield. The dodecahedron embodiment is sufficiently lightweight to be suitable for

    摘要翻译: 用于飞机的中子谱仪由堆叠在吸收层上的固态检测器覆盖的一系列基底提供。 多达12个将中子转化为质子的基底被一层吸收材料覆盖,作为质子吸收剂,探测器放置在该层内,以计算通过吸收层的质子。 通过使用12个探测器,覆盖了中子能量范围。 中子谱仪的优选十二面体实施例是固体的聚乙烯十二面体组件,其具有由固体状态检测器覆盖的12个表面面,该固体检测器堆叠在由铝构成的吸收层上。 每个吸收层根据光谱中的中子的最小和最大能量构造不同的厚度。 在这种布置中,12个表面五边形面中的每一个提供聚乙烯基底,以将中子转换成质子,由一层吸收材料覆盖,作为质子吸收体,检测器堆叠在吸收层上,以计数通过的质子 吸收层。 十二面体组件同心地容纳在用作外护罩的钛球壳内。 十二面体实施例足够轻巧以适合

    Angular time synchronized directional radiation sensor
    4.
    发明授权
    Angular time synchronized directional radiation sensor 失效
    角度时间同步方向辐射传感器

    公开(公告)号:US6100530A

    公开(公告)日:2000-08-08

    申请号:US207897

    申请日:1998-11-23

    IPC分类号: G01T1/29 G01V5/06 G01T1/18

    CPC分类号: G01V5/06 G01T1/2914

    摘要: An angular time-synchronized directional radiation sensor is provided to indicate the direction, or distribution of directions, of incident gamma radiation, and consequently, to locate sources of radioactivity emitting these photons. The angular time-synchronized directional radiation sensor comprises a rotating radiation sensing means, interacting with the incident radiation to produce light flashes, together with a stationary photomultiplier tube that converts the light flashes to electrical pulses that are counted by a data collection means. A synchronous motor enables the radiation sensing means to complete a 360.degree. scan within 1 second to reduce the time needed for measuring from hours to only a few minutes. The data collection means calculates an angle of rotation at a corresponding fraction of the 360.degree. scan to rapidly indicate the direction of a radiation source. In one embodiment, the data collection means is a computer. The radiation sensing means can be a scintillator assembly.

    摘要翻译: 提供角度时间同步的定向辐射传感器以指示入射的伽马辐射的方向或方向的分布,并且因此定位发射这些光子的放射性源。 角度时间同步的定向辐射传感器包括旋转的辐射感测装置,与入射的辐射相互作用以产生闪光,以及固定的光电倍增管,其将闪光转换成由数据采集装置计数的电脉冲。 同步电机使辐射检测装置能够在1秒内完成360度扫描,以减少从数小时到仅数分钟的测量所需的时间。 数据采集​​装置计算在360度扫描的相应部分的旋转角度,以快速指示辐射源的方向。 在一个实施例中,数据收集装置是计算机。 辐射感测装置可以是闪烁体组件。

    Radiochromic dosimeter
    5.
    发明授权
    Radiochromic dosimeter 失效
    放射性变色剂量计

    公开(公告)号:US5120969A

    公开(公告)日:1992-06-09

    申请号:US751378

    申请日:1991-08-26

    IPC分类号: G01T1/06

    CPC分类号: G01T1/06

    摘要: A radiochromic dosimeter for use as a tactical or like dosimeter for measuring absorbed ionizing, radiation dose of relatively high range. This dosimeter includes an outer barrel, a first ultraviolet light opaque, ionizing radiation transparent tube, a liquid solution of leuko dye disposed in the first tube, a second ultraviolet light opaque, ionizing radiation transparent tube, a liquid solvent disposed in the second tube, the tubes having end sealing beads, the outer barrel having end tube supports, a filter disposed next to output ends of the tubes, a lens disposed next to the filter for viewing filtered light circles, and a light adjuster for controlling light amount passing into the second tube input end.

    摘要翻译: 用作测量吸收电离,相对较高范围的辐射剂量的战术或类似剂量计的放射性色素剂量计。 该剂量计包括外筒,第一紫外线不透明,电离辐射透明管,设置在第一管中的白细胞染料的液体溶液,第二紫外线不透明,电离辐射透明管,设置在第二管中的液体溶剂, 所述管具有端部密封珠,所述外筒具有端部管支撑件,邻近所述管的输出端设置的过滤器,邻近所述过滤器设置的用于观察过滤光圈的透镜;以及光调节器,用于控制进入 第二管输入端。

    Neutron spectrometer with titanium proton absorber

    公开(公告)号:US06678343B1

    公开(公告)日:2004-01-13

    申请号:US10189880

    申请日:2002-07-02

    IPC分类号: G01T300

    CPC分类号: G01T3/08

    摘要: A neutron spectrometer is provided by a series of substrates covered by a solid-state detector stacked on an absorbing layer. As many as 12 substrates that convert neutrons to protons are covered by a layer of absorbing material, acting as a proton absorber, with the detector placed within the layer to count protons passing through the absorbing layer. By using 12 detectors the range of neutron energies are covered. The flat embodiment of the neutron spectrometer is a chamber, a group of detectors each having an absorber layer, with each detector separated by gaps and arranged in an egg-crate-like structure within the chamber. Each absorber layer is constructed with a different thickness according to the minimum and maximum energies of neutrons in the spectrum. In this arrangement, each of the 12 surface facets provides a polyethylene substrate to convert neutrons to protons, covered by a layer of absorbing material, acting as a proton absorber, with the detector stacked on the absorbing layer to count protons passing through the absorbing layer.

    Alpha, beta, and gamma monitor for measuring concentrations of ionizing radiation emitters in ambient air or other media
    7.
    发明授权
    Alpha, beta, and gamma monitor for measuring concentrations of ionizing radiation emitters in ambient air or other media 失效
    Alpha,beta和gamma监测器,用于测量环境空气或其他介质中电离辐射发射体的浓度

    公开(公告)号:US06346709B1

    公开(公告)日:2002-02-12

    申请号:US09516083

    申请日:2000-03-01

    IPC分类号: H01J4708

    CPC分类号: G01T1/142

    摘要: A low cost and simple technique for measurement of radioactive contaminants in the air, soil, or in buildings is provided. The alpha, beta gamma radiation monitor comprises a thin window and two more removable radiation windows on top of a pancake-shaped conductive plastic chamber, with a microscope and a carbon fiber electrometer within the chamber protruding through the chamber's side wall, and the microscope and electrometer opposing each other. Within the chamber the microscope is optically focused on the electrometer fiber. Three radiation windows are provided: one admits alpha particles, beta particles and gamma radiation to the chamber, another admits beta particles and gamma radiation, and a third one admits only gamma radiation. Thus one can measure or observe alpha, beta, and gamma radiation, beta and gamma radiation, or only gamma radiation. The present invention's configuration allows the concentration of each type of radiation to be independently determined. The radiation that penetrates one of the radiation windows generates an ionization charge within the chamber that causes a carbon fiber image to move along a scale within the microscope as a function of time to produce the desired reading. In the case of airborne alpha emitting contaminants either the concentration of alpha particles or the total alpha energy of the emission can be measured.

    摘要翻译: 提供了用于测量空气,土壤或建筑物中的放射性污染物的低成本和简单的技术。 α,β伽马辐射监测器包括薄的窗口和两个更可移除的辐射窗口,位于饼状导电塑料室的顶部,显微镜和腔室内的碳纤维静电计数器突出穿过室的侧壁,显微镜和 静电计彼此相对。 在室内,显微镜被光学聚焦在静电计量纤维上。 提供三个辐射窗口:一个允许α粒子,β粒子和γ辐射到腔室,另一个允许β粒子和γ射线,另外一个允许只有伽马射线。 因此,可以测量或观察α,β和γ辐射,β和γ辐射,或者仅测量γ辐射。 本发明的结构允许各种类型的辐射的浓度被独立地确定。 穿透辐射窗口之一的辐射在腔室内产生电离电荷,导致碳纤维图像作为时间的函数沿着显微镜内的刻度移动以产生期望的读数。 在机载α发射污染物的情况下,可以测量α粒子的浓度或发射的总α能量。

    Method and apparatus for measuring angular differential dose of ionizing
radiation
    8.
    发明授权
    Method and apparatus for measuring angular differential dose of ionizing radiation 失效
    用于测量电离辐射角度差分剂量的方法和装置

    公开(公告)号:US5703370A

    公开(公告)日:1997-12-30

    申请号:US816821

    申请日:1997-03-18

    IPC分类号: G01T1/14 G01T1/185 G01T1/02

    CPC分类号: G01T1/14 G01T1/185

    摘要: A sensor from a carbon fiber, self-reading electrometer type of dosimeter made with a radically modified ionization chamber in order to determine the angular differential dose of ionizing radiation. The chamber is flat and its size is increased so that it is operable from intensities of 100 nGy(T) h.sup.-1 to 10.sup.4 Gy(T) h.sup.-1. This performance range can be accomplished by the addition of capacitors to reduce the dosimeter's basic sensitivity. The capacitors should be connected in parallel between the electrometer assembly and ground. Additionally, the ionization chamber is lined, or in effect "sandwiched," between a low atomic number "low Z" material and a high atomic number "high Z" material. In one embodiment, a hermetically sealed plastic housing is lined on one surface with a lead (Pb) plate and the remainder of the housing is painted on the inside except the side with the lead plate) with a carbon paint. In so modifying the chamber, there will be a difference in the ionization effect coming from the lead side than from the low Z material side. By this difference in signal, one can determine the angular differential dose of radiation.

    摘要翻译: 使用自动修正电离室制作碳纤维传感器,自读式静电计型剂量计,以确定电离辐射的角度差分剂量。 室是平坦的,其尺寸增加,使得其可以从100nGy(T)h-1到104Gy(T)h-1的强度操作。 该性能范围可以通过添加电容器来实现,以减少剂量计的基本灵敏度。 电容器应在静电计组件和地之间并联连接。 此外,电离室在低原子序数“低Z”材料和高原子序数“高Z”材料之间衬里或实际上“夹在”之间。 在一个实施例中,气密密封的塑料壳体在一个表面上带有铅(Pb)板,并且壳体的其余部分被涂覆在具有碳涂料的除了铅板的一侧之外的内部)。 在改变腔室时,从引线侧的离子化效应与低Z材料侧的电离效应将存在差异。 通过信号差异,可以确定辐射的角度差分剂量。

    Radiation sensor dosimetry circuit
    9.
    发明授权
    Radiation sensor dosimetry circuit 失效
    辐射传感器剂量测量电路

    公开(公告)号:US5477050A

    公开(公告)日:1995-12-19

    申请号:US260853

    申请日:1994-06-16

    IPC分类号: G01T1/02

    CPC分类号: G01T1/026

    摘要: A radiation sensor of the type that acquires a charge or voltage proportil to a dose of radiation. Upon obtaining a predetermined value to the associated voltage proportional to the dose, the voltage is caused to be discharged. A counter keeps track of the number of discharges which is proportional to the total dose of radiation to which the radiation sensor has been exposed. The radiation sensor is thereby prevented from achieving a high charge or voltage which affects the accuracy of the radiation sensor. A calculator and a clock are used to display the value of the dose in any convenient way, such as in relation to tissue dose or average dose rate for a given period of time.

    摘要翻译: 该类型的辐射传感器获得与辐射剂量成比例的电荷或电压。 当获得与剂量成比例的相关电压的预定值时,使电压被放电。 计数器跟踪与放射线传感器暴露于的辐射的总剂量成比例的放电次数。 从而防止辐射传感器实现影响辐射传感器精度的高电荷或电压。 计算器和时钟用于以任何方便的方式显示剂量的值,例如相对于给定时间段的组织剂量或平均剂量率。

    Dose and dose rate sensor for the pocket radiac
    10.
    发明授权
    Dose and dose rate sensor for the pocket radiac 失效
    口袋辐射剂量和剂量率传感器

    公开(公告)号:US4893017A

    公开(公告)日:1990-01-09

    申请号:US260425

    申请日:1988-10-14

    IPC分类号: G01T1/02 G01T3/08

    CPC分类号: G01T3/08 G01T1/026

    摘要: A radiation detector which registers the radiation absorbed during the Prt Initial Radiation (PIR) phase following the detonation of a battlefield nuclear device is disclosed. The dose and dose rate attributable to gamma rays may be measured when the dose rate is low, and the total dose attributable to neutron and gamma ray radiation can be determined separately when the dose rate is high. Two silicon photodiodes are arranged on opposite sides of a slab of polyethylene to gather protons scattered by the incident neutron flux. A third photodiode is set next to a slab of silicon such that its depleted layer is surrounded by silicon. All three diodes are sensitive to gamma ray radiation. When the dose rate is low, the three diodes gather gamma ray dose information. When the dose rate is high, the two diodes adjacent to the polyethylene register combined neutron and gamma ray dose information while the remaining diode registers predominantly gamma ray dose information. Analog to digital converters are used to change the analog signals from the diodes to digital signals appropriate for a microprocessor. These digital signals can be combined with dose data stored in the microprocessor to determine gamma ray dose rates and neutron and gamma ray doses.

    摘要翻译: 公开了一种辐射探测器,其记录在战场核装置引爆之后的即时初始辐射(PIR)期间吸收的辐射。 当剂量率低时可以测量归因于γ射线的剂量和剂量率,并且当剂量率高时,可以分别确定归因于中子和γ射线辐射的总剂量。 两个硅光电二极管布置在聚乙烯板的相对两侧,以收集由入射中子通量散射的质子。 将第三光电二极管设置在硅片的旁边,使得其耗尽层被硅包围。 所有三个二极管对伽马射线辐射敏感。 当剂量率低时,三个二极管收集伽马射线剂量信息。 当剂量率高时,与聚乙烯寄存器相邻的两个二极管组合了中子和伽马射线剂量信息,而剩余的二极管主要以伽马射线剂量信息为主。 模数转换器用于将二极管的模拟信号更改为适用于微处理器的数字信号。 这些数字信号可以与存储在微处理器中的剂量数据组合,以确定伽马射线剂量率和中子和γ射线剂量。