Neutron dosimeter based on current integral electronics system

An electronic system and neutron dose technology, applied in the measurement of neutron radiation, scientific instruments, radiation measurement, etc., can solve the problem of leakage counting, inability to independently distinguish pulse signals, and neutron dosimeters cannot accurately detect neutron dosimeters. Sub-radiation dose value and other issues, to achieve the effect of improving detection accuracy and avoiding missed counts

Active Publication Date: 2022-04-12
INST OF HIGH ENERGY PHYSICS CHINESE ACAD OF SCI +1
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Problems solved by technology

However, when multiple neutrons in the pulse radiation field are simultaneously incident on the probe in a very short time, the pulse counting amplifier circuit cannot independently distinguish the pulse signals of multiple neutrons, resulting in the inability to accurately record the number of current pulse signals, and leakage occurs. The counting situation makes the neutron dosimeter unable to accurately detect the current neutron radiation dose value, thereby reducing the detection accuracy of the neutron dosimeter

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  • Neutron dosimeter based on current integral electronics system
  • Neutron dosimeter based on current integral electronics system
  • Neutron dosimeter based on current integral electronics system

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Embodiment Construction

[0045] Example embodiments will now be described more fully with reference to the accompanying drawings. Example embodiments may, however, be embodied in many forms and should not be construed as limited to the examples set forth herein; rather, these embodiments are provided so that this disclosure will be thorough and complete, and will fully convey the concept of example embodiments to those skilled in the art. The described features, structures, or characteristics may be combined in any suitable manner in one or more embodiments. In the following description, numerous specific details are provided in order to give a thorough understanding of embodiments of the present disclosure.

[0046] The described features, structures, or characteristics may be combined in any suitable manner in one or more embodiments. In the following description, numerous specific details are provided in order to give a thorough understanding of embodiments of the present disclosure. However, on...

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Abstract

The invention provides a neutron dosimeter based on a current integration type electronics system, and belongs to the technical field of radiation dose detection. The neutron dosimeter comprises a probe module and a circuit module. Wherein the probe module comprises an outer-layer moderator, a metal layer, a polymer layer, an inner-layer moderator and a counter which are sequentially arranged from outside to inside, and neutrons can generate nuclear reaction in the counter to generate current signals. The circuit module comprises a signal amplification circuit and a data processing circuit, the signal amplification circuit can convert the current signal into a voltage signal, and the data processing circuit can convert the voltage signal into the current signal and can determine the radiation dose value of neutrons according to the current signal. In the detection process, the current neutron radiation dose value can be determined by acquiring the total charge quantity generated by the current neutrons without recording the number of the current pulse signals. Therefore, missed counting is avoided, and the detection precision of the neutron dosimeter is improved.

Description

technical field [0001] The present disclosure relates to the technical field of radiation dose detection, in particular to a neutron dosimeter based on a current integrating electronic system. Background technique [0002] The neutron dosimeter is a common tool to detect the neutron radiation dose value in the radioactive workplace. The dosimeter generally uses an electronic system based on a pulse counting amplifier circuit. However, when multiple neutrons in the pulsed radiation field are incident into the probe at the same time in a very short time, the pulse counting amplifier circuit cannot independently distinguish the pulse signals of multiple neutrons, resulting in the inability to accurately record the number of current pulse signals, and leakage occurs. The counting situation makes the neutron dosimeter unable to accurately detect the current neutron radiation dose value, thereby reducing the detection accuracy of the neutron dosimeter. [0003] The above informat...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G01T3/00
CPCY02E30/30
Inventor 阎明洋张震马忠剑张银鸿李玉文梁婧陈飞
Owner INST OF HIGH ENERGY PHYSICS CHINESE ACAD OF SCI
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