Device for real-time measurement of energy spectrum of neutrons in reactor

A real-time measurement and neutron technology, applied in the field of nuclear radiation detection, can solve the problem of obtaining energy spectrum for a long time, and achieve the effect of high resolution and small device volume

Active Publication Date: 2018-08-14
CHINA INST FOR RADIATION PROTECTION
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0009] The purpose of the present invention is to provide a device for real-time measurement of the neutron energy spectrum in the reactor to solve the technical problem

Method used

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  • Device for real-time measurement of energy spectrum of neutrons in reactor
  • Device for real-time measurement of energy spectrum of neutrons in reactor
  • Device for real-time measurement of energy spectrum of neutrons in reactor

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Embodiment Construction

[0034] The specific implementation manners of the present invention will be further described below in conjunction with the accompanying drawings.

[0035] An exemplary device of the present invention for real-time measurement of neutron energy spectrum in a reactor is as image 3 As shown, including 5 fiber optic probes (corresponding to image 3 probes 1-5), 5 quartz optical fibers, and 5 circuit modules (corresponding to image 3 Photon detector and counting unit 1-5) and computer+software data processing system.

[0036] (1) Optical fiber probe and optical fiber

[0037] Each fiber optic probe includes a silica fiber end and a detection material coated on the silica fiber end for generating scintillation light. The detection materials coated on the five fiber optic probes are respectively (ZnS:Ag powder is commercially available, and the mass percentage of Ag is between 0.001% and 0.01%):

[0038] ①The molar ratio is 1:1 6 LiF+ZnS:Ag;

[0039] ②The molar ratio is 1:1...

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Abstract

The invention belongs to the nuclear radiation detection technical field and relates to a device for the real-time measurement of the energy spectrum of neutrons in a reactor. The device comprises a plurality of optical fiber probes, a plurality of optical fibers, a circuit module and a computer data processing system; each optical fiber probe comprises an optical fiber tail end and a detection material which coats the optical fiber tail end and is used for generating scintillation light; one end of each optical fiber is connected with each optical fiber probe, and the other end of the each optical fiber is connected with the circuit module, so that the optical fiber can be used for transmitting the scintillation light; the circuit module is used for converting and amplifying the signals of the scintillation light generated by the optical fiber probes into digital signals; and the computer data processing system is used for receiving the digital signal data from the circuit module, processing the digital signal data and rendering neutron spectra at positions where each optical fiber probe is located. With the device of the invention adopted, the signals can be acquired in real time, and neutron energy spectrum distribution at the positions where the optical fiber probes are arranged can be obtained, and therefore, and a defect that an existing activation sheet measurement technology requires a plurality of times of irradiation and spectrum unfolding and takes a long time to obtain energy spectra can be eliminated.

Description

technical field [0001] The invention belongs to the technical field of nuclear radiation detection and relates to a device for real-time measurement of neutron energy spectrum in a reactor. Background technique [0002] The measurement of neutron distribution is very important for the study of reactors and neutron generators. Various methods are currently available for such measurements. BF 3 or 3 He proportional counter tubes can be used for real-time measurement of neutrons, but such detectors are usually difficult to penetrate into narrow spaces such as the gaps of fuel elements. In recent years, a small optical fiber neutron detector has been developed internationally, and the volume of this type of detector can be 1mm 3 Even smaller, for easy access into the reactor and real-time measurement of neutrons. [0003] The composition of the detection system of this type of small fiber optic neutron detector is as follows: figure 1 shown. The scintillation light enters...

Claims

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Application Information

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IPC IPC(8): G01T1/36
CPCG01T1/362Y02E30/30
Inventor 陈宝维朱庆福周琦李健杨中建白召乐谢伟民程昊杨楠
Owner CHINA INST FOR RADIATION PROTECTION
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