热中子防护Gd/Al复合材料的设计  

The Design of Gd/Al Composite Material for Thermal Neutron Protection

作　　者：徐天寒 张叶[1] 戴耀东[1] XU Tianhan;ZHANG Ye;DAI Yaodong(Academy of Materials Science and Technology,Nanjing University of Aeronautics and Astronautics,Nanjing 210016,China)

机构地区：[1]南京航空航天大学材料科学与技术学院,南京210016

出　　处：《材料导报》2021年第22期22121-22124,共4页Materials Reports

基　　金：“十三五”核能开发科研第五批项目。

摘　　要：随着核电和核动力的发展,热中子防护材料需具备屏蔽性能好、质量轻和机械强度高等特点,而Al基复合材料特别是Al基稀土材料正具备这一特点,因此受到研究人员的广泛关注。本文针对热中子屏蔽Gd/Al复合材料,采用蒙特卡罗方法计算了材料的热中子透射率,通过对比分析得到功能粒子Gd对纯Al材料的中子透射率的改善效果要优于功能粒子B_(4)C的结论。当Gd/Al复合热中子屏蔽材料的厚度大于2 mm,Gd质量含量应不需大于6%。最后将本文的研究成果应用在乏燃料储存格架材料优化设计中,并得到Gd/Al复合材料辐射性能最佳配比是Gd质量含量4%、复合材料厚度3 mm。The rapid development of nuclear power facility requires the shielding material to be light-weight,and strong in structure,which draws resea-chers’attention to Al based material for its characteristic.This paper focuses on the thermal neutron shielding performance of Al/Gd composites,the thermal neutron transmittance of the composites with different functional particles were computed with Monte Carlo method.By comparing the result,we conclude that Gd particle does a better job than B_(4)C in improving the shielding performance.Also,we find the content of Gd in the Gd/Al material should not go beyond 6% when the neutron shielding material has a thickness of 2 mm.Finally,we successfully apply this research to optimizing the design for spent fuel storage rack material and conclude that the best thickness and Gd content is 3 mm and 4%respectively.

关 键 词：Gd/Al复合材料 热中子 B_(4)C 蒙特卡罗方法 

分 类 号：TL77[核科学技术—辐射防护及环境保护]