The Advancement of Neutron Shielding Materials for the Storage of Spent Nuclear Fuel

被引:48
作者
Fu, Xuelong [1 ,2 ]
Ji, Zhengbo [1 ]
Lin, Wei [1 ]
Yu, Yunfeng [1 ]
Wu, Tao [1 ]
机构
[1] Jiangsu Vocat & Tech Coll Finance & Econ, Dept Mech & Elect Engn, Huaian 223003, Jiangsu, Peoples R China
[2] Nanjing Univ Aeronaut & Astronaut, Coll Mat Sci & Technol, Nanjing 211106, Peoples R China
关键词
HEAVY-METAL OXIDE; MECHANICAL-PROPERTIES; GAMMA-RAY; CORROSION BEHAVIOR; THERMAL-PROPERTIES; STAINLESS-STEEL; EPDM RUBBER; COMPOSITE; MICROSTRUCTURE; DESIGN;
D O I
10.1155/2021/5541047
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
With the development of nuclear industry, spent nuclear fuel (SNF) generated from nuclear power plants arouses people's attention as a result of its high radioactivity, and how to guarantee the reliable operation of nuclear facilities and the staff's safety occupies a crucial position. To avoid the lethal irradiation, a lot of functional neutron shielding composites have been developed to transform fast neutrons into thermal neutrons which can be absorbed with high macroscopic cross-sectional elements. Irradiation characteristics of nuclear industry have promoted the advancement of neutron shielding materials. Here, we review the latest neutron shielding materials for the storage of spent nuclear fuel containing additives such as boron carbide (B4C), boron nitride (BN), boric acid (H3BO3), and colemanite. Different types of neutron shielding materials, including metal matrix alloys, polymer composites, high density concrete, heavy metals, paraffin, and other neutron shielding composites with high macroscopic cross-sectional elements, arediscussed. The elemental composition, density, and thermal and mechanical properties of neutron shielding materials are also summarized and compared.
引用
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页数:13
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