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:
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:
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:
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:
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:
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:
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:
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:
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:
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.