Measurement and evaluation of neutron spectra in nuclear power plants

被引：0
|
作者：
Wang P. [1 ]
Yang J. [1 ]
Zhang H. [1 ]
Ren Z. [2 ]
Wang R. [3 ,4 ]
Zhang J. [1 ]
机构：
[1] National Institute of Metrology, Beijing
[2] Institute of Applied Electronics, China Academy of Engineering Physics, Mianyang
[3] School of Radiation Medicine and Protection, Department of Medicine, Soochow University, Suzhou
[4] Collaborative Innovation Center of Radiation Medicine of Jiangsu Higher Education Institutions, Suzhou
来源：
Harbin Gongcheng Daxue Xuebao/Journal of Harbin Engineering University | 2022年 / 43卷 / 11期
关键词：
ambient dose equivalent; genetic algorithm; iterative algorithm; maximum entropy algorithm; multisphere neutron spectrometer; neutron spectrum; nuclear power plant; response function;
D O I：
10.11990/jheu.202206016
中图分类号：
学科分类号：
摘要：
A multisphere neutron spectrometer is used to measure the neutron spectrum at several locations in different reactor plants of the Qinshan nuclear power plant to address the ineffectiveness of routine calibration of neutron ambient dose equivalent meter in correcting the onsite measurement results. The response function of the multisphere neutron spectrometer is calculated, and the experimental calibration of the monoenergetic neutron response is conducted. Three algorithms, namely the maximum entropy, iterative, and genetic algorithms, are used to reveal the spectrum of the measurement results. A variety of neutron radiation parameters are deduced from the spectrum for the verification of the spectrum results, and the direct measurement results of the neutron dosimeter LB6411 and FHT762 are corrected for the onsite measurements. The following results are presented. The neutron spectra of the three algorithms agree well, and the folding count rates agree with the measured count rates within an uncertainty range, indicating that the measurement process and the spectrum results are reliable. The maximum entropy and iterative algorithms have the best spectrum results and should be considered preferentially. Meanwhile, the genetic algorithm is slightly worse but is suitable for the case with an unknown radiation environment. The uncertainty of the neutron ambient dose equivalent H∗(10) derived from the energy spectrum results is 8% ~ 10%. The direct measurement results of FHT762 are 25% ~ 61% larger, and the LB6411 results are 4% ~ 21% smaller compared with the spectrum results. This finding confirms the feasibility of the spectrum method to improve the accuracy of H∗(10) measurement onsite in nuclear power plants. © 2022 Editorial Board of Journal of Harbin Engineering. All rights reserved.
引用
收藏
页码：1621 / 1629
页数：8
相关论文
共 23 条
  • [1] CHEN Jun, LI Chunjuan, WEI Kexin, Et al., Measurement of neutron energy spectra and ambient dose equivalent rates at workplaces of a nuclear power plant, Journal of astronautic metrology and measurement, 34, 3, pp. 45-50, (2014)
  • [2] GRIFFITH R V, PALFALVI J, MADHVANATH U., Compendium of neutron spectra and detector responses for radiation protection purposes, pp. 1-274, (1990)
  • [3] Compendium of neutron spectra and detector responses for radiation protection purposes: supplement to technical reports series no. 318 [ M ], (2001)
  • [4] COSACK M, LESIECKI H., Dose equivalent survey meters [J], Radiation protection dosimetry, 10, 1, pp. 111-119, (1985)
  • [5] ISO 8529 - 1:2021. Reference neutron radiations-Part 1: Characteristics and methods of production: [ S], (2021)
  • [6] ISO 12789-1: 2008. Reference radiation fields-simulated workplace neutron fields-Part 1: characteristics and methods of production, (2008)
  • [7] ICRP publication 74: conversion coefficients for use in radiological protection against external radiation [ M], pp. 1-205, (1996)
  • [8] ALEYNIK V, BAYANOV B, BURDAKOV A, Et al., New technical solution for using the time-of-flight technique to measure neutron spectra, Applied radiation and isotopes, 69, 12, pp. 1639-1641, (2011)
  • [9] JOHNSON C H, TRAIL C C., Proton-recoil neutron spectrometer[ J], Review of scientific instruments, 27, 7, pp. 468-474, (1956)
  • [10] BRAMBLETT R L, EWING R I, BONNER T W., A new type of neutron spectrometer, Nuclear instruments and methods, 9, 1, pp. 1-12, (1960)
123