Research on the test, measurement and ambient dose equivalent conversion for a multisphere neutron spectrometer

Ning LYU; Huiping GUO; Aiguo SHANG; Kuo ZHAO; Wenhui LYU; Qizhan XIAO; Mingyan SUN; Zequn DU; Rui MENG; Liwen CHEN; Kai WANG; Zhi CAO

doi:10.11889/j.0253-3219.2018.hjs.41.120403

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Research on the test, measurement and ambient dose equivalent conversion for a multisphere neutron spectrometer

NUCLEAR ELECTRONICS AND INSTRUMENTATION | 更新时间：2021-05-19

- Research on the test, measurement and ambient dose equivalent conversion for a multisphere neutron spectrometer
- NUCLEAR TECHNIQUES Vol. 41, Issue 12, Article number: 120403(2018)
- 作者机构：
  
  1.火箭军工程大学西安 710025
  2.中国人民解放军92609部队北京 100077
  3.中国人民解放军96035部队通化 134000
  4.中国人民解放军96871部队宝鸡 721000
  5.中国人民解放军91515部队三亚 572000
- 作者简介：
- 基金信息：
- DOI：10.11889/j.0253-3219.2018.hjs.41.120403
  CLC： TL817
- Received：11 September 2018，
  
  Revised：31 October 2018，
  
  Published：10 December 2018
- 稿件说明：
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Ning LYU, Huiping GUO, Aiguo SHANG, et al. Research on the test, measurement and ambient dose equivalent conversion for a multisphere neutron spectrometer[J]. Nuclear techniques, 2018, 41(12): 120403
DOI：

Ning LYU, Huiping GUO, Aiguo SHANG, et al. Research on the test, measurement and ambient dose equivalent conversion for a multisphere neutron spectrometer[J]. Nuclear techniques, 2018, 41(12): 120403 DOI： 10.11889/j.0253-3219.2018.hjs.41.120403.

摘要

以辐射场全能段中子能谱获取及周围剂量当量转换为目的，针对一套以

He正比计数器为探测器的多球中子谱仪，介绍了采用脉冲幅度分析法进行中子-γ甄别，准确测量中子计数率的方法；测量并获取了实验室本底环境中子、Am-Be中子源、氘氘中子管连续出射中子三种辐射场的中子能谱，并予以分析；基于中子能谱进行周围剂量当量转换，分析了不同能量段中子所占的剂量比重，发现快中子是主要贡献者；在比较测量中，对三种单慢化体中子剂量仪器产生的误差进行了理论分析，并给出了依靠多球中子谱仪测准中子周围剂量当量的三点建议。多球中子谱仪可以直接测算周围剂量当量，可以指导其它中子剂量仪器的标校，还可以针对具体能量段进行中子防护设计，精准有效指导外照射剂量防护工作的开展。

Abstract

Background

Neutron ambient dose equivalent is closely related to neutron energy. Acquisition of the energy spectrum is necessary to calculate the ambient dose equivalent accurately in the neutron radiation field.

Purpose

This study aims at the ambient dose equivalent calculation by shakedown test of multi sphere neutron spectrometer (MNS).

Methods

First of all

pulse height analysis (PHA) method was used for neutron/γ discrimination to precisely measure neutron count rate. Then the neutron energy spectrum was successfully obtained and carefully analyzed in three neutron radiation fields:laboratory background

Am-Be neutron source and DD tube emergency neutron. Neutron fluence was converted into ambient dose equivalent consulting the conversion coefficient recommended by International Commission on Radiological Protection (ICRP) report No.74

and dose contribution weight from neutron in different energy groups was analyzed. Finally

comparison test was made against three other instruments with mono moderator respectively

errors between MNS and them were analyzed theoretically.

Results

Neutron ambient dose equivalent converted from energy spectrum measured by MNS was consistent with the other three dose instruments. No matter what kind of the neutron radiation field is

fast neutrons are the main contributors to the dose.

Conclusion

PHA and pulse height spectrum monitoring is the critical point for neutron energy spectrum measurement. MNS can be used to measure and calculate neutron ambient dose equivalent directly

guide optimal reference radiation for other neutron dose instruments calibration

and radiation protection design against neutron of special energy groups.

关键词

Keywords

references

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