TY - Jour A2 - Zulauf，Alexander Au - Fu，Xuelong Au - 吉，郑博·林，魏奥 - 宇，云峰奥 - 吴，陶福 - 2021DA - 2021/05/07 - 中子屏蔽的进步Materials for the Storage of Spent Nuclear Fuel SP - 5541047 VL - 2021 AB - 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 (B_4.c），氮化硼（BN），硼酸（H._3.博_3.）和科学土。不同类型的中子屏蔽材料，包括金属基质合金，聚合物复合材料，高密度混凝土，重金属，石蜡和其他中子屏蔽复合材料，具有高宏观横截面元素，Alediscussed。还总结并比较了中子屏蔽材料的元素组成，密度和热和机械性能。SN - 1687-6075 UR - HTTPS://Doi.org/10.1155/2021/5541047 DO - 10.1155 / 2021/5541047 JF - 核设施科学与技术PB - Hindawi Kw - ER -