Preliminary shielding analysis in support of the CSNS target station shutter neutron beam stop design

The construction of China Spallation Neutron Source （CSNS） has been initiated in Dongguan, Guangdong, China. Thus a detailed radiation transport analysis of the shutter neutron beam stop is of vital importance. The analyses are performed using the coupled Monte Carlo and multi-dimensional discrete o...

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Published inChinese physics C Vol. 35; no. 8; pp. 791 - 795
Main Author 张斌 陈义学 王伟金 杨寿海 吴军 殷雯 梁天骄 贾学军
Format Journal Article
LanguageEnglish
Published IOP Publishing 01.08.2011
Subjects
China
Design engineering
Mathematical models
Neutron beams
Plugs
Shielding
Shutters
Two dimensional
中子束
人身安全
剂量分布
屏蔽设计
快门
散裂中子源
标准限值
蒙特卡洛
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Summary:The construction of China Spallation Neutron Source （CSNS） has been initiated in Dongguan, Guangdong, China. Thus a detailed radiation transport analysis of the shutter neutron beam stop is of vital importance. The analyses are performed using the coupled Monte Carlo and multi-dimensional discrete ordinates method. The target of calculations is to optimize the neutron beamline shielding design to guarantee personal safety and minimize cost. Successful elimination of the primary ray effects via the two-dimensional uncollided flux and the first collision source methodology is also illustrated. Two-dimensional dose distribution is calculated. The dose at the end of the neutron beam line is less than 2.5 μSv/h. The models have ensured that the doses received by the hall staff members are below the standard limit required.
Bibliography:ZHANG Bin, CHEN YI-Xue, WANG Wei-Jin,YANG Shou-Hai, WU Jun, YIN Wen, LIANG Tian-Jiao, JIA Xue-Jun（1 School of Nuclear Science and Engineering, North China Electric Power University, Zhuxinzhuang Dewai, Beijing 102206, China 2 Institute of Physics, Chinese Academy of Sciences, Beijing 100190, China）
11-5641/O4
neutron transport, spallation source shielding, discrete ordinates method
The construction of China Spallation Neutron Source （CSNS） has been initiated in Dongguan, Guangdong, China. Thus a detailed radiation transport analysis of the shutter neutron beam stop is of vital importance. The analyses are performed using the coupled Monte Carlo and multi-dimensional discrete ordinates method. The target of calculations is to optimize the neutron beamline shielding design to guarantee personal safety and minimize cost. Successful elimination of the primary ray effects via the two-dimensional uncollided flux and the first collision source methodology is also illustrated. Two-dimensional dose distribution is calculated. The dose at the end of the neutron beam line is less than 2.5 μSv/h. The models have ensured that the doses received by the hall staff members are below the standard limit required.
ObjectType-Article-2
SourceType-Scholarly Journals-1
ObjectType-Feature-1
content type line 23
ISSN:1674-1137
0254-3052
2058-6132
DOI:10.1088/1674-1137/35/8/017