摘要
文章采用蒙特卡罗程序耦合抽样技巧,对西安脉冲堆中子照相孔道外的屏蔽体进行改建设计计算,确定了中子照相孔道口出射束流参数和多种材料组合的屏蔽参数。实验测试结果表明,理论计算可靠,达到了改建指标。
Coupling sampling skill used in Monte-Carlo code MCNP/4B was applied in rebuilding design of the shield of neutron radiography at Xi＇an pulsed reactor in order to calculate the radiation field parameter of the experiment bore and the shield thickness of multi-material shield. The tests show that the reliability of calculation results satisfies the rebuilding requirements.
出处
《原子能科学技术》
EI
CAS
CSCD
北大核心
2006年第5期544-548,共5页
Atomic Energy Science and Technology
关键词
中子照相
辐射屏蔽
剂量
反照率
neutron radiography
radiation shield
dose
albedo
