辐射防护2017，Vol.37Issue(2)：94-99,6.
Am-Be中子源屏蔽优化设计的蒙特卡罗模拟研究
Monte Carlo simulation on optimal design of neutron shielding for Am-Be source
摘要
Abstract
Hydrogen-rich material is currently used as shielding material in the conventional container of 241 Am -Be neutron source,which causes the protective bucket large size,low efficiency and difficult to transport to well logging field.In this work,two different shielding materials are determined.And Monte Carlo simulation method is employed to optimize the thickness and combination mode of that filling material.Results show that the optimal volume and weight of protective tank is 0.187 m3 and 430 kg,respectively.Particularly,13 centimeters thick tungsten is select as the inner shielding layer and 18 cm thick boron polyethylene is chosen for thermal neutron-absorbent as the outer layer,and the radiation levels of concerned location is evaluated using MCNP code.It can be conclude that the dose rate of the outside is less than 0.025 mSv·h-1,which meet the requirement of relevant standards.关键词
241Am-Be中子源/屏蔽/优化设计/MCNP/钨/硼聚乙烯Key words
241Am-Be neutron source/shielding/optimal design/MCNP/tungsten/boron polyethylene分类
能源科技引用本文复制引用
吴赫,张锋,李亚芬,韩忠悦,顾明翔..Am-Be中子源屏蔽优化设计的蒙特卡罗模拟研究[J].辐射防护,2017,37(2):94-99,6.基金项目
国家自然科学基金资助项目(No.41374125,41574119) （No.41374125,41574119）
国家重大油气专项(No.2011ZX0520-002) （No.2011ZX0520-002）
中央高校基本科研业务费专项资金资助(14CX05011A,15CX06008A). （14CX05011A,15CX06008A）
