中国散裂中子源靶站中子通道初步屏蔽计算分析  

Shielding for Neutron Beam Extraction Pipes of Chinese Spallation Neutron Source

作　　者：张斌[1] 陈义学[1] 杨寿海[1] 殷雯[2] 

机构地区：[1]华北电力大学核科学与工程学院,北京102206 [2]中国科学院物理研究所,北京100190

出　　处：《原子能科学技术》2010年第2期210-214,共5页Atomic Energy Science and Technology

基　　金：国家自然科学基金面上项目资助(10875042);北京市科技新星计划资助项目(2007B058)

摘　　要：基于中国散裂中子源靶站中子通道设计,采用二维离散纵标程序DORT对中子导出通道各种设计方案的屏蔽效果进行计算分析。计算得出二维剂量场分布及通道中心处剂量当量率轴向分布,并得到较优化的屏蔽方案及模型,确保谱仪大厅内工作人员接受的剂量低于规定的标准。结果表明,未安装谱仪的中子通道屏蔽模型中心含有SS316合金钢时的屏蔽效果较好,剂量在辐射防护标准以下,符合设计要求。中子孔道开闭装置屏蔽模型中前端加入钨板屏蔽效果较好,并随钨板长度的增加,屏蔽效果提高。Based on the design of Chinese Spallation Neutron Source （CSNS） target station neutron beam extraction pipes, shielding efficiency was evaluated using the two dimensional discrete ordinates transport code DORT for different design models. Two- dimensional dose field distribution and the axial distribution were calculated. Mean while, an optimal shielding model was obtained from the calculation. The model ensures that the received doses of the hall staff members below the required standard limit. The results show that the shielding model inserted with SS316 steel has a better shielding efficiency than that without SS316 steel. In addition, the model of the shutter front with tungsten plate has a better efficiency than the others. The shielding efficiency of the vary length tungsten plate was discussed.

关 键 词：中国散裂中子源 中子导出通道 离散纵标法 屏蔽 

分 类 号：TL77[核科学技术—辐射防护及环境保护] TL99