Radiation sensor dosimetry circuit
    11.
    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
    12.
    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。

    Charge transport tactical dosimeter
    13.
    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。

    Dodecahedron neutron spectrometer with titanium proton absorber for aircraft
    14.
    发明授权
    Dodecahedron neutron spectrometer with titanium proton absorber for aircraft 失效
    十二面体中子谱仪与飞机的钛质子吸收器

    公开(公告)号:US06717999B1

    公开(公告)日:2004-04-06

    申请号:US10224231

    申请日:2002-08-19

    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 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 titanium. 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 airborne and satellite applications.

    摘要翻译: 中子谱仪由堆叠在吸收层上的固体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钛构成的吸收层上。 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。 十二面体的实施例足够轻便,适用于机载和卫星应用。

    Neutron spectrometer
    15.
    发明授权
    Neutron spectrometer 失效
    中子光谱仪

    公开(公告)号:US06714616B1

    公开(公告)日:2004-03-30

    申请号:US10006735

    申请日:2001-11-01

    IPC分类号: G21H100

    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.

    摘要翻译: 中子谱仪由堆叠在吸收层上的固体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。 中子谱仪的扁平实施例是一个室,一组检测器,每个检测器都具有吸收层,每个检测器由间隙分隔并且在室内以蛋壳状结构排列。 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。 在该布置中,12个表面小面中的每一个提供聚乙烯基底,以将中子转化为质子,由质子吸收材料层覆盖,其中检测器堆叠在吸收层上以计数通过吸收层的质子 。

    Directional radiation detector and imager
    16.
    发明授权
    Directional radiation detector and imager 失效
    定向辐射探测器和成像仪

    公开(公告)号:US5665970A

    公开(公告)日:1997-09-09

    申请号:US687095

    申请日:1996-07-03

    CPC分类号: G01T1/18

    摘要: A radiation sensor and/or imager is formed by sandwiching two materials having different atomic numbers (Z) around a radiation detector, such as scintilator or Geiger-Mueller type radiation counters, or solid state radiation detectors, such as those made of silicon). In one embodiment of the present invention, a thin layer of lead (Pb) is placed on one side of a Geiger-Mueller radiation counter and a layer of Lucite.TM. is disposed on the opposite side. One example, of a preferred Geiger-Mueller counter which may be used in the present invention is a modified pancake Geiger-Mueller counter with thin ruby mica windows, approximately 2.8 mg/cm.sup.2 thick on both sides. By disposing a high Z material on one side of a radiation detector such as a Geiger-Mueller (GM) or a Scintillator Counter (SC) and a low Z material on an opposite side of either type of the counter, it is possible to detect the photo-Compton electrons emitted from the high or low Z material in the forward or backward directions and the attenuation of the emitted electrons by the high Z material. Because the Geiger-Mueller or scintillation counter can detect single events, the directional radiation detector according to the present invention can detect radiation intensities down to background radiation levels, which is approximately 0.15 .mu.Gy h.sup.-1. Given the difference in the count rate (or intensity), the direction of the radiation source may be easily calculated by simply rotating the detector or by having two counters displaced in different angles (such as 180 degrees) so as to be able to take the difference of the number counts (or mirrors of the intensities).

    摘要翻译: 辐射传感器和/或成像器通过将辐射检测器(例如闪烁体或盖革 - 米勒型辐射计数器)或诸如由硅制成的固态辐射检测器的固态辐射检测器(例如由硅制成的固体放射线检测器)包围在具有不同原子序数(Z)的两种材料形成。 在本发明的一个实施例中,将薄层铅(Pb)放置在盖革 - 米勒辐射计数器的一侧上,并且Lucite TM层设置在相对侧。 可用于本发明的优选Geiger-Mueller计数器的一个实例是具有薄的红宝石云母窗的改进的薄饼Geiger-Mueller计数器,两侧厚度约为2.8mg / cm2。 通过在诸如盖革 - 米勒(GM)或闪烁计数器(SC)的辐射检测器的一侧上设置高Z材料,并且在任一类型的计数器的相对侧上设置低Z材料,可以检测 从高Z或低Z材料向前或向后发射的光 - 康普顿电子和高Z材料发射的电子的衰减。 由于Geiger-Mueller或闪烁计数器可以检测单个事件,根据本发明的定向辐射检测器可以检测到低至背景辐射水平的辐射强度,其大约为0.15ug Gyh-1。 给定计数率(或强度)的差异,可以通过简单地旋转检测器或通过使两个计数器以不同的角度(例如180度)移位来容易地计算辐射源的方向,以便能够 数量差异(或强度的镜像)。

    Rugged alpha particle counter
    17.
    发明授权
    Rugged alpha particle counter 失效
    坚固的α粒子计数器

    公开(公告)号:US5059803A

    公开(公告)日:1991-10-22

    申请号:US554508

    申请日:1990-07-19

    IPC分类号: G01T1/18 H01J47/02

    CPC分类号: H01J47/02 G01T1/18 Y10S250/02

    摘要: An alpha particle counter for detecting individual alpha particles with a detection medium which is ambient air. Energetic alpha particles from radioactive decay products or other sources enter the detector volume through a durable wire screen window and ionize the ambient air detection medium. Ions of one polarity are driven to the central collector electrode by an electric field due to a battery imposed potential difference between the outer electrode and the central electrode and housing. One pulse is produced for each alpha particle losing its energy in the detector. The counting efficiency is substantially one hundred percent (100%) and is relatively noise free because the collector electrode is essentially at ground potential. The collector electrode signal is amplified in a field effect transistor (FET) emitter follower circuit, the output of which is fed to an external counter. Rugged construction and minimum maintenance are inherent features of this alpha particle detector.

    摘要翻译: 用于用具有环境空气的检测介质检测单个α粒子的α粒子计数器。 来自放射性衰变产物或其他来源的能量α粒子通过耐用的丝网筛入口进入检测器体积,并使环境空气检测介质电离。 由于外部电极与中心电极和壳体之间的电池电位差,电极将一个极性的离子通过电场驱动到中心集电极。 每个α粒子在检测器中失去其能量产生一个脉冲。 计数效率基本上为100%(100%),并且由于集电极基本上处于地电势,所以相对无噪声。 集电极信号在场效应晶体管(FET)射极跟随器电路中放大,其输出被馈送到外部计数器。 坚固耐用的结构和最小的维护是这种α粒子检测器的固有特性。

    Solid state gamma ray dosimeter which measures radiation in terms of
absorption in a material different from the detector material
    18.
    发明授权
    Solid state gamma ray dosimeter which measures radiation in terms of absorption in a material different from the detector material 失效
    固体γ射线剂量计,其测量与不同于检测器材料的材料的吸收方面的辐射

    公开(公告)号:US4859853A

    公开(公告)日:1989-08-22

    申请号:US152128

    申请日:1988-02-04

    IPC分类号: G01T1/02 G01T1/24

    CPC分类号: G01T1/026 G01T1/24

    摘要: A solid state gamma ray dosimeter which measures radiation in terms of absorption in a material different from the detector material. A solid state detector, an amplifier, an analog-to-digital interface and a microprocessor are combined in circuit to correct for differences between absorption of radiation in detector material and absorption in other materials, especially tissue. A suitable cladding may surround the detector. A method of generating dose translation data for calibrating the microprocessor is also disclosed. The solid state detector is attached to a multichannel analyzer circuit and subject to known doses of various monochromatic gamma rays. Output pulses from the detector are amplified and introduced into the multichannel analyzer. The spectrum produced is used to determine an average channel number (or pulse height) for a given dose of monochromatic radiation. The given dose is in units specific to material different from the detector material. The partial dose represented by a single detector pulse at that energy is computed. Partial doses for other energies are likewise computed. Dose translation data associates a partial dose with a given detector pulse height. Dose translation data is set in the microprocessor of the dosimeter. Such dose translation data can be used to calculate total dose and dose rate in units peculiar to material other than detector material.

    摘要翻译: 固体γ射线剂量计,其测量与不同于检测器材料的材料的吸收方面的辐射。 固态检测器,放大器,模拟 - 数字接口和微处理器组合在电路中,以校正检测器材料中的辐射吸收与其他材料,特别是组织中的吸收之间的差异。 合适的包层可围绕检测器。 还公开了一种产生用于校准微处理器的剂量转换数据的方法。 固态检测器连接到多通道分析器电路并经受已知剂量的各种单色γ射线。 来自检测器的输出脉冲被放大并被引入多通道分析器。 产生的光谱用于确定给定剂量的单色辐射的平均通道数(或脉冲高度)。 给定的剂量是以与检测器材料不同的材料特有的单位。 计算由该能量处的单个检测器脉冲表示的部分剂量。 同样计算其他能量的部分剂量。 剂量转换数据将部分剂量与给定的检测器脉冲高度相关联。 在剂量计的微处理器中设置剂量转换数据。 这样的剂量翻译数据可用于以除检测器材料以外的材料特有的单位计算总剂量和剂量率。

    Solid state nuclear radiation detector circuit with constant sensitivity
    19.
    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。

    Neutron spectrometer with aluminum proton absorber
    20.
    发明授权
    Neutron spectrometer with aluminum proton absorber 失效
    中子光谱仪与铝质子吸收剂

    公开(公告)号:US06954512B1

    公开(公告)日:2005-10-11

    申请号:US10198667

    申请日:2002-07-17

    IPC分类号: G01T3/08 G21H1/00

    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.

    摘要翻译: 中子谱仪由堆叠在吸收层上的固体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。 中子谱仪的扁平实施例是一个室,一组检测器,每个检测器都具有吸收层,每个检测器由间隙分隔并且在室内以蛋壳状结构排列。 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。 在该布置中,12个表面小面中的每一个提供聚乙烯基底,以将中子转化为质子,由质子吸收材料层覆盖,其中检测器堆叠在吸收层上以计数通过吸收层的质子 。