环境γ谱仪对大气中放射性核素活度浓度响应系数测量方法

何林锋; 唐方东; 赵超

doi:10.11889/j.0253-3219.2018.hjs.41.080401

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环境γ谱仪对大气中放射性核素活度浓度响应系数测量方法

核电子学与仪器 | 更新时间：2021-05-19

- 环境γ谱仪对大气中放射性核素活度浓度响应系数测量方法
- A method to determine the response coefficient of environmental gamma spectrometer to airborne radionuclide concentration
- 核技术 2018年41卷第8期文章编号：080401
- 作者机构：
  
  上海市计量测试技术研究院上海 201203
- 作者简介：
  
  [ "何林锋, 男, 1977年出生, 2005年于上海大学获硕士学位, 高级工程师, 主要从事电离辐射计量标准和测量技术研究工作", "HE Linfeng, male, born in 1977, graduated from Shanghai University with a master's degree in 2005, senior engineer, engaged in ionizing radiation measurement standard and technology research" ]
  赵超, E-mail:zhaoc@simt.com.cn ZHAO Chao, E-mail:zhaoc@simt.com.cn
- 基金信息：
  
  上海市科学技术委员会科研计划项目(16DZ2292300);上海市质量技术监督局科技计划项目(2015-ZX001)
- DOI：10.11889/j.0253-3219.2018.hjs.41.080401
  中图分类号： TL84;TL751;X837
- 收稿日期：2018-03-28，
  
  修回日期：2018-04-09，
  
  纸质出版日期：2018-08
- 稿件说明：
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何林锋, 唐方东, 赵超. 环境γ谱仪对大气中放射性核素活度浓度响应系数测量方法[J]. 核技术, 2018,41(8):080401

Linfeng HE, Fangdong TANG, Chao ZHAO. A method to determine the response coefficient of environmental gamma spectrometer to airborne radionuclide concentration[J]. Nuclear techniques, 2018, 41(8): 080401
何林锋, 唐方东, 赵超. 环境γ谱仪对大气中放射性核素活度浓度响应系数测量方法[J]. 核技术, 2018,41(8):080401 DOI： 10.11889/j.0253-3219.2018.hjs.41.080401.

Linfeng HE, Fangdong TANG, Chao ZHAO. A method to determine the response coefficient of environmental gamma spectrometer to airborne radionuclide concentration[J]. Nuclear techniques, 2018, 41(8): 080401 DOI： 10.11889/j.0253-3219.2018.hjs.41.080401.

摘要

为建立一种准确实用的环境γ谱仪对大气中放射性核素活度浓度响应系数的测量方法，构建活度浓度响应系数理论估算模型，并基于探测效率空间分布的两条假设，推导出两种简化估算模型。蒙特卡罗方法模拟结果显示：模拟结果与实验室测量结果相符，在所有测量点位两者差异均小于6%；对于一款典型NaI γ谱仪，采用两种简化估算模型引入的误差分别不超过0.1%和10%。现场测试结果显示：该方法现场适用性良好，两台环境γ谱仪对大气中

137

Cs的活度浓度响应系数分别为6.49min

-1

·Bq

-1

·m

和2.62min

-1

·Bq

-1

·m

。

Abstract

Background

In the last decade

a large number of environmental gamma spectrometers have been installed to monitor ambient radionuclide in the environmental radiation monitoring stations in China. However

the response coefficients to airborne radionuclide concentration of most facilities were unknown.

Purpose

This study aims to establish an accurate and practical method for determining the response coefficient to airborne radionuclide concentration of the environmental gamma spectrometers.

Methods

Based on two assumptions on the spatial distribution of the facility's detection efficiency

a theoretical model was proposed and simplified. Subsequently. Monte Carlo simulation method was utilized to analyze the deviation contributed by the two assumptions for several common radionuclides quantitatively. Simultaneously

the detection efficiency spatial distribution of a self-developed gamma spectrometer which consists of a typical NaI(Tl) crystal (76.2 mm×76.2 mm) was measured in an

137

Cs expose experiment to verify the accuracy of Monte Carlo simulation method. Lastly

the method for determining the response coefficient was established by using the simplified theoretical model

and applied to two environmental gamma spectrometers in field.

Results

The relative difference between the experimental and simulated detection efficiency of the self-developed gamma spectrometer was less than 6% at every measurement position. According to the Monte Carlo simulation results of the typical gamma spectrometer

relative deviations of response coefficients to several common airborne radionuclides contributed by the two assumptions were less than 0.1% and 10% respectively. In the field test

the changing trend of the detection efficiency was similar to the simulated results

and the response coefficients to airborne

137

Cs of the two facilities were 6.49 min

-1

·Bq

-1

·m

and 2.62 min

-1

·Bq

-1

·m

respectively.

Conclusion

The results of Monte Carlo simulation indicated that the simplified model was acceptable for environmental radiation monitoring field

and the applicability of this method had been validated through field test.

关键词

Keywords

references

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