移动式放射性气体监测仪能量响应的优化设计

doi:10.11889/j.0253-3219.2018.hjs.41.030401

Nuclear Techniques ›› 2018, Vol. 41 ›› Issue (3): 30401-030401.doi: 10.11889/j.0253-3219.2018.hjs.41.030401

• NUCLEAR ELECTRONICS AND INSTRUMENTATION • Previous Articles Next Articles

Optimization design for energy response of the mobile radioactive gas monitor

ZHOU Xuemei^1,2, LIU Guimin^1,2, CHEN Yongzhong^1,2

1. Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Jiading Campus, Shanghai 201800, China;
2. Center for Thorium Molten Salt Reactor System, Chinese Academy of Sciences, Shanghai 201800, China

Received:2017-10-25 Revised:2017-11-21 Online:2018-03-10 Published:2018-03-14
Supported by:
Supported by Strategic Priority Program of Chinese Academy of Sciences (No.XD02001003)

Abstract

Abstract: [Background] The mobile radioactive gas monitor responses differently to gamma rays at different energies. [Purpose] This study aims to accurately measure the dose of gamma radiation monitor by means of compensation for energy response. [Methods] Energy responses of NaI(Tl) crystals in the monitor in different lead-hole models were simulated using Monte Carlo N Particle Transport Code (MCNP) software. Various sizes of shielding lead hole were selected to compare the standard deviations of different models, and the optimum size of shielding lead hole was obtained. [Results & Conclusion] The simulation result shows that the energy response of monitor is best compensated when the radius of hole is 3.0 cm and thickness of shielding lead is 0.5 cm.

Key words: Mobile radioactive gas monitor, MCNP, Energy response compensation, Lead shield

CLC Number:

TL812⁺.1

ZHOU Xuemei, LIU Guimin, CHEN Yongzhong. Optimization design for energy response of the mobile radioactive gas monitor[J].Nuclear Techniques, 2018, 41(3): 30401-030401.

References

1 曾兵,葛良生,郭生良,等.NaI (Tl)晶体对γ射线响应函数的蒙特卡罗模拟[J].核电子学与探测技术,2009,29(2):394-397.DOI:10.3969/j.issn.0258-0934.2009.02.040.ZENG Bing,GE Liangsheng,GUO Shengliang,et al.Monte Carlo simulation for the response function of NaI (Tl) crystal to γ-ray[J].Nuclear Electronics &Detection Technology,2009,29(2):394-397.DOI:10.3969/j.issn.0258-0934.2009.02.040.
2 王仁波,杨奎.MC模拟碘化钠探测器能量响应及其优化设计[J].核电子学与探测技术,2015, 35(2):188-192.DOI:10.3969/j.issn.0258-0934.2015.02.018.WANG Renbo,YANG Kui.Monte Carlo simulation and optimization design for NaI detector energy response[J].Nuclear Electronics&Detection Technology,2015,35(2):188-192.DOI:10.3969/j.issn.0258-0934.2015.02.018.
3 王成竹,张佳,沈杨,等.GM计数管能量响应补偿研究的新思路[J].核电子学与探测技术,2013,33(10):1215-1218.DOI:10.3969/j.issn.0258-0934.2013.10.011.WANG Chengzhu,ZHANG Jia,SHEN Yang,et al.A research of energy response compensation for G-M counter[J].Nuclear Electronics&Detection Technology,2013,33(10):1215-1218.DOI:10.3969/j.issn.0258-0934.2013.10.011.
4 杨金合,杨坤杰,吴麒麟,等.碘化钠探测器能量响应补偿的模拟研究[J].核电子学与探测技术,2016,36(10):1062-1065.DOI:10.3969/j.issn.0258-0934.2016.10.017.YANG Jinhe,YANG Kunjie,WU Qilin,et al.A simulation research of energy response compensation for NaI detector[J].Nuclear Electronics&Detection Technology,2016,36(10):1062-1065.DOI:10.3969/j.issn.0258-0934.2016.10.017.
5 王红艳,肖雪夫,马永福.用蒙特卡罗方法研究球形充气电离室的能量响应特性[J].原子能科学技术,2006,40(6):28-32.DOI:10.3969/j.issn.1000-6931.2006.06.019.WANG Hongyan,XIAO Xuefu,MA Yongfu.Energy response characteristics of ionization chamber by using Monte-Carlo method[J].Atomic Energy Science and Technology,2006,40(6):28-32.DOI:10.3969/j.issn.1000-6931.2006.06.019.
6 ICRP.Conversion coefficients for use in radiological protection against external radiation[R].ICRP Publication 74,Oxford:Pergamon Press,1996.
7 郭生良.γ能谱的蒙特卡罗计算方法探讨与模拟软件设计[D].成都:成都理工大学,2008.GUO Shengliang.Monte Carlo simulation for γ spectrum and simulation software design[D].Chengdu:Chengdu University of Technology,2008.
8 吴祥余.不同尺寸γ射线探测器响应函数及探测效率的蒙特卡罗模拟[D].成都:成都理工大学,2009.WU Xiangyu.The simulation of response function and detection efficiency for γ-ray detector of different sizes by Monte Carlo method[D].Chengdu:Chengdu University of Technology,2009.
9 国家质量监督检验检疫总局.JJG393-2003:辐射防护用X、γ辐射剂量当量(率)仪和监测仪检规程[S].2003.General Administration of Quality Supervision,Inspection and Quarantine of the People's Republic of China.JJG393-2003:X and gamma radiation dose equivalent (rate) meters and monitors used in radiation protection[S].2003.

[1]	XU Su, ZHANG Qingxian, HE Qingju, WU Tao, ZHANG Gang, SHI Cong, SUN Kun, XIAO Yunlong. Comparison of different Monte Carlo simulation software for simulating neutron depth profiling [J]. Nuclear Techniques, 2018, 41(9): 90203-090203.
[2]	HU Chundong, LI Mengting, XIE Yahong, CHEN Yuqing. Radiation analysis and simulation of the CFETR neutral beam system prototype with hydrogen beam [J]. Nuclear Techniques, 2018, 41(9): 90603-090603.
[3]	LIU Zhujun, YANG Yiwei, ZHENG Lei, LIU Rong, YANG Chaowen, WANG Mei. Measurement and analysis of the ²³²Th(n,2n) reaction rate in a polyethylene shell with DT neutrons [J]. Nuclear Techniques, 2018, 41(6): 60502-060502.
[4]	XU Bingbing, XU Kun, YE Minyou, MAO Shifeng, LEI Mingzhun, PENG Xuebing. Neutronics-thermal hydraulics coupling module for CFETR integration design platform [J]. Nuclear Techniques, 2018, 41(1): 10601-010601.
[5]	ZHANG Xiaowen, YAO Ya, YI Cheng, LI Mi, YANG Rong, JIANG Tianjiao, YANG Sheng. Radiation shielding efficiency and optimization of concrete incorporated with bismuth oxide [J]. Nuclear Techniques, 2017, 40(6): 60201-060201.
[6]	ZHANG Luyu, WANG Zhimin, BAI Huaiyong, CHEN Jinxiang, ZHANG Guohui. Simulation of the core configuration schemes for the AP1000 reactor by the Monte Carlo code [J]. Nuclear Techniques, 2017, 40(4): 40604-040604.
[7]	ZHANG Zhenchao, ZUO Guoping, TAN Junwen, ZHOU Yang, ZHANG Fan. Locating radioactive source based on three coupled-crystals directional detector of γ rays [J]. Nuclear Techniques, 2017, 40(10): 100402-100402.
[8]	HE Jie, XIA Xiaobin, CAI Jun, PAN Deng, PENG Yu, HUANG Jianping, ZHANG Guoqing. Temperature field analysis for the main shielding of the 2-MW thorium-based molten salt experimental reactor [J]. Nuclear Techniques, 2016, 39(4): 40601-040601.
[9]	YANG Litao, CHEN Chaofeng, HUANG Yanjun, HE Yi, SHANGGUAN Zhihong. Simulation of gamma spectra continuous monitoring in seawater [J]. Nuclear Techniques, 2016, 39(3): 30203-030203.
[10]	NIE Xingchen, LI Jia, ZHAO Pinghui, ZHU Qingjun. Application and comparison of global variance reduction methods employed in Monte Carlo neutron transport for CFETR [J]. Nuclear Techniques, 2016, 39(3): 30501-030501.
[11]	HE Dan, SONG Yingming, ZOU Shuliang, XU Shoulong, WANG Xiaodong, ZHU Zhichao, TAN Zhengan, HE Zhifeng, WANG Xinlin. Design of shielding-performance testing-device for reactors construction shielding-material based on 252Cf source [J]. Nuclear Techniques, 2015, 38(9): 90604-090604.
[12]	HOU Jingjing, WANG Shiqing, CAI Yun, WANG Zhanhe, XIANG Qian, LIU Haifeng. Conceptual core design of small traveling wave reactors based on coupled code of MCNP-ORIGEN2 [J]. Nuclear Techniques, 2015, 38(8): 80603-080603.
[13]	HE Zehong, YE Minyou, WANG Zhongwei, MAO Shifeng, XU Kun. MCNP coupled with post-processing software application development [J]. Nuclear Techniques, 2015, 38(6): 60601-060601.
[14]	ZHENG Honglong, TUO Xianguo, SHI Rui, YANG Gang, DENG Chao, CAO Wen, LIU Yao. Monte Carlo simulations of efficiency function of HPGe detector to point sources and determination of its parameters [J]. Nuclear Techniques, 2015, 38(4): 40201-040201.
[15]	LI Lei, LI Xiaoyan, HUANG Wei, JIANG Shubin, WU Xiaoli, YANG Guixia. Study on improving MCNP computational efficiency of dose rate for a single-rack cobalt irradiation facility [J]. Nuclear Techniques, 2015, 38(3): 30201-030201.

Optimization design for energy response of the mobile radioactive gas monitor

PDF (PC)

Like

Knowledge

Abstract

Cite this article

share this article

References

Related Articles 15

Metrics

Comments

Recommended 10