国产B4C颗粒增强铝基复合材料的耐辐照性能研究  

Study on radiation resistance of domestic B4C particle reinforced aluminum matrix composite

作　　者：石悠 刘桂荣[2] 张亚东[3] 宁冬 陈锦 杨义忠 SHI You;LIU Gui-rong;ZHANG Ya-dong;NING Dong;CHEN Jin;YANG Yi-zhong(Shanghai Nuclear Engineering Research ＆ Design Institute Co., Ltd., Shanghai 200233, China;Advanced Technology ＆ Materials Co., Ltd., Beijing 100094, China;China Institute of Atomic Energy, Beijing 102413, China;Antai-heyuan Nuclear Energy Technology ＆ Materials Co., Ltd., Beijing 100094, China)

机构地区：[1]上海核工程研究设计院有限公司,上海200233 [2]安泰科技股份有限公司,北京100094 [3]中国原子能科学研究院,北京102413 [4]安泰核原新材料科技有限公司,北京100094

出　　处：《粉末冶金工业》2018年第2期30-34,共5页Powder Metallurgy Industry

摘　　要：采用粉末冶金工艺制备的国产B4C颗粒增强铝基复合材料中子吸收板开展辐照试验研究,中子吸收板经受累积快中子注量4.22×1019n/cm2、γ射线剂量为4.75×1011rad的辐照后,对材料各项性能进行测试,包括表面形貌、尺寸、质量、密度、力学性能（抗拉强度、硬度和伸长率）及10B面密度,并与辐照前的测试结果进行对比分析。结果表明,在中子和γ射线的辐照作用下,复合材料试样的抗拉强度和硬度提高,伸长率下降,表面形貌未发生明显变化,尺寸、质量、密度及10B面密度均无显著改变。The B4C particle reinforced Al-matrix composite used as neutron absorber plates were prepared by powder metallurgy method. After being subjected to a radiation test with fast neutron influence up to 4.22×1019 n/cm2 and gamma-ray dose reaching 4.75×1011 rad,the properties of the material,including surface morphology,size,mass,density,mechanical properties（tensile strength,hardness and elongation）as well as boron-10（10 B）areal density,were tested and compared with those before irradiation. The results show that the tensile strength and hardness of the composite are improved with the elongation decreased,the surface morphology has not changed obviously,and the size,mass,density and10 B areal density have not changed significantly under the irradiation of neutron and gamma rays.

关 键 词：B4C 颗粒增强铝基复合材料 乏燃料贮存格架 中子吸收板 辐照 10B面密度 

分 类 号：TB333[一般工业技术—材料科学与工程] TF125[冶金工程—粉末冶金]