基于模拟现场中子场的电子式个人剂量仪响应实验研究

刘立业; 陈法国; 李会; 陈红涛; 唐智辉; 李德源; 黄政林; 张凯

doi:10.3724/j.0253-3219.2026.hjs.49.250006

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基于模拟现场中子场的电子式个人剂量仪响应实验研究

核电子学与仪器 | 更新时间：2026-02-13

- 基于模拟现场中子场的电子式个人剂量仪响应实验研究
- Experimental study on neutron response of electronic personal dosimeters based on simulated workplace neutron field
- 核技术 2026年49卷第2期文章编号：020402
- 作者机构：
  
  1.中国辐射防护研究院太原 030006
  2.辐射安全与防护山西省重点实验室太原 030006
  3.中核集团辐射防护技术重点实验室太原 030006
  4.中国原子能科学研究院北京 102413
  5.瑞昌核物理应用研究院瑞昌 332200
- 作者简介：
  
  刘立业，男，1978年出生，2010年于清华大学获博士学位，研究领域为辐射监测与防护
  陈法国，E-mail：chenfaguo@cirp.org.cn
- 基金信息：
  
  the Research on Neutron Dosimetry Monitoring Technology(YY24010702)
- DOI：10.3724/j.0253-3219.2026.hjs.49.250006
  中图分类号： TL84
- 收稿：2025-01-08，
  
  修回：2025-06-23，
  
  纸质出版：2026-02-15
- 稿件说明：
移动端阅览
刘立业,陈法国,李会等.基于模拟现场中子场的电子式个人剂量仪响应实验研究[J].核技术,2026,49(02):020402.

LIU Liye,CHEN Faguo,LI Hui,et al.Experimental study on neutron response of electronic personal dosimeters based on simulated workplace neutron field[J].NUCLEAR TECHNIQUES,2026,49(02):020402.
刘立业,陈法国,李会等.基于模拟现场中子场的电子式个人剂量仪响应实验研究[J].核技术,2026,49(02):020402. DOI： 10.3724/j.0253-3219.2026.hjs.49.250006. CSTR： 32193.14.hjs.CN31-1342/TL.2026.49.250006.

LIU Liye,CHEN Faguo,LI Hui,et al.Experimental study on neutron response of electronic personal dosimeters based on simulated workplace neutron field[J].NUCLEAR TECHNIQUES,2026,49(02):020402. DOI： 10.3724/j.0253-3219.2026.hjs.49.250006. CSTR： 32193.14.hjs.CN31-1342/TL.2026.49.250006.

摘要

中子剂量测量因中子能量范围宽和能量响应的复杂性而面临准确性挑战；电子式中子个人剂量仪（Electronic neutron personal dosimeters， n-EPDs）在不同能谱下的响应差异显著，常用同位素中子源校准可能导致现场剂量测量偏差。为了研究中子能谱分布对n-EPDs响应的影响，利用

252

Cf同位素中子源、氘-氚（D-T）加速器中子源以及重水、钨、铁、石墨、聚乙烯等材料，建立了4种不同能谱分布的中子辐射场，并结合多球中子谱仪的实测能谱和蒙特卡罗计算的入射角度分布，测试了两种市售电子式中子个人剂量仪（n-EPDs）的响应差异。结果显示：在

252

Cf裸源参考辐射场中，多球实测能谱与标准谱主要能区的相对偏差在±10%以内；4个中子场的注量平均能量为0.12~2.00 MeV、剂量平均能量为0.75~3.65 MeV、谱平均注量-剂量转换系数为51.17~390.3 pSv·cm

；两种市售n-EPDs对4个中子场的最大响应差异分别为5.7和6.7倍。研究表明，当利用同位素中子源进行校准时，n-EPDs读数通常会高估现场实际的个人剂量当量，需要特别关注能量响应、现场能谱分布及入射方向对测量准确性的影响。

Abstract

Background

Neutron dose measurement faces challenges due to the wide range of neutron energy and the complexity of energy response. The response of electronic neutron personal dosimeters (n-EPDs) varies significantly under different energy spectra

and calibration with isotope neutron sources may lead to on-site dose measurement deviations.

Purpose

This study aims to investigate the influences of neutron energy spectrum distribution and incident direction on the response of n-EPDs.

Methods

Firstly

252

Cf isotope neutron source

D-T accelerator neutron source and materials such as heavy water

tungsten

iron

graphite and polyethylene

were used to establish four neutron radiation fields with different energy spectra. Then

the Bonner neutron spectrometer was employed to measure neutron energy spectra

while the incident angle distributions were calculated using Monte Carlo method. Finally

the response differences of two commercial elec

tric personal neutron dosimeters (n-EPDs) were experimentally tested.

Results

The relative deviation between measured spectrum and standard spectrum of

252

Cf reference radiation field is within ±10% in the main energy regions. For four neutron fields

the fluence-averaged neutron energy ranges from 0.12 MeV to 2.00 MeV

the dose-averaged neutron energy ranges from 0.75 MeV to 3.65 MeV

and the spectra-averaged conversion coefficient ranges from 51.17 pSv·cm

to 390.3 pSv·cm

. The maximum response differences of two commercial n-EPDs to four neutron fields are 5.7 and 6.7 times

respectively.

Conclusions

Results of this study indicate that when using isotope neutron sources for calibration

n-EPDs readings often overestimate the actual individual dose equivalent in workplace

hence special attentions need to be paid to the impacts of energy response

neutron energy spectrum

and incident direction on measurement accuracy.

关键词

Keywords

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