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Determination method for average neutron energy of high-flux deuterium-tritium neutron generator

A technology of neutron generator and average energy, which is applied in the direction of neutron radiation measurement, instruments, measuring devices, etc., can solve the problems of inaccurate measurement results and inability to measure neutron energy, etc., and achieve the effect of accurate measurement results

Active Publication Date: 2017-10-10
LANZHOU UNIVERSITY
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  • Abstract
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  • Claims
  • Application Information

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Problems solved by technology

[0005] The purpose of the present invention is to provide a method for determining the average neutron energy of a high-throughput deuterium-tritium neutron generator, which solves the problem that the existing measurement method cannot measure neutron energy at a relatively extreme level, and the measurement result is inaccurate

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  • Determination method for average neutron energy of high-flux deuterium-tritium neutron generator
  • Determination method for average neutron energy of high-flux deuterium-tritium neutron generator
  • Determination method for average neutron energy of high-flux deuterium-tritium neutron generator

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Embodiment Construction

[0020] The present invention will be described in detail below in conjunction with specific embodiments.

[0021] refer to figure 1 , the embodiment method of the present invention is as follows:

[0022] S1. Use 59 Co(n,2n) 58 Co with 59 Co(n,p) 59 Fe section ratio determines the average energy calculation formula under high-flux and long-time irradiation conditions;

[0023] Set the subscript Co to indicate 9 Co(n,2n) 58 Co, subscript Fe means 59 Co(n,p) 59 Fe. then there is

[0024]

[0025]

[0026] σ is the reaction cross section, ε P is the measured characteristic ray full-energy peak efficiency; I γ is the intensity of characteristic rays; η is the measured isotope abundance; S=1-e -λT Indicates the growth factor of the remaining nuclei; λ is the decay constant; T is the total neutron irradiation time; M is the mass of the sample; D=e -λT1 -e -λT2 For the measurement collection factor, T 1 is the time interval from the end of irradiation to the beg...

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Abstract

The present invention discloses a determination method for the average neutron energy of a high-flux deuterium-tritium (D-T) neutron generator. According to the technical scheme of the invention, an average energy calculation formula in the high-flux and long-time irradiation condition is determined according to the cross-section ratio of 59Co(n,2n)58Co to 59Co(n,p)59Fe. After that, a D-T source is adopted to irradiate four groups of experiment samples, wherein each group of samples is composed of two Nb pieces, one Zr piece and one Co piece. Meanwhile, the gamma energy spectrum is measured by a gamma spectrometer. After that, the gamma energy spectrum measured during the experiment is processed and then the counted number of the total energy peaks of corresponding characteristic gamma rays is obtained. The gamma energy spectrum is subjected to spectrum unscrambling treatment, and then a true number of total energy peaks is obtained. Finally, the corresponding data are substituted into the average energy calculation formula obtained in the first step, and then the reliability of the method is verified. According to the method, the neutron energy in relatively extreme conditions can be measured, and the measuring result of the method is accurate.

Description

technical field [0001] The invention belongs to the technical field of neutron application in experimental nuclear physics, and relates to a method for determining average neutron energy of a high-throughput deuterium-tritium (D-T) neutron generator. Background technique [0002] The neutron energy produced by the D-T neutron source can reach near the 14MeV energy region, within this range, T(d,n) 4 He has a large reaction cross section and a high neutron yield. At the same time, the monochromaticity of the D-T neutron source is good, and the reaction cross section under the single energy point can be measured. In the neutron nuclear reaction test, the first physical quantity considered and determined is the incident neutron energy, which is the basis for making the reaction cross section meaningful. Currently, 14MeV neutrons are mainly obtained by D-T reactions. There are recoil proton method, nuclear reaction method, time-of-flight method, etc. to determine the neutron e...

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G01T3/00
CPCG01T3/00
Inventor 兰长林江历阳解保林张毅阮锡超聂阳波潘小东彭猛邱奕嘉
Owner LANZHOU UNIVERSITY