用于乏核燃料运输与储存的中子屏蔽材料的进展

The Advancement of Neutron-Shielding Materials for the Transportation and Storage of Spent Nuclear Fuel.

作者信息

Qi Zhengdong, Yang Zhong, Li Jianping, Guo Yongchun, Yang Guichun, Yu Yang, Zhang Jiachen

机构信息

School of Materials and Chemical Engineering, Xi'an Technological University, Xi'an 710021, China.

School of Electrical and Mechanical Engineering, Xinjiang Institute of Technology, Aksu 843100, China.

出版信息

Materials (Basel). 2022 Apr 30;15(9):3255. doi: 10.3390/ma15093255.

DOI:10.3390/ma15093255

PMID:35591589

原文链接:https://pmc.ncbi.nlm.nih.gov/articles/PMC9099936/

Abstract

In this paper, the mechanism of neutron absorption and common reinforced particles is introduced, and recent research progress on different types of neutron-shielding materials (borated stainless steels, B/Al Alloy, BC/Al composites, polymer-based composites, and shielding concrete) for transportation and wet or dry storage of spent fuel is elaborated, and critical performance is summarized and compared. In particular, the most widely studied and used borated stainless steel and BC/Al composite neutron-absorption materials in the field of spent fuel are discussed at length. The problems and solutions in the preparation and application of different types of neutron-shielding materials for spent fuel transportation and storage are discussed, and their research priorities and development trends are proposed.

摘要

本文介绍了中子吸收机理及常见增强颗粒，阐述了用于乏燃料运输及湿存或干存的不同类型中子屏蔽材料（含硼不锈钢、硼铝合金、碳化硼/铝复合材料复合材料物聚合物基复合材料和屏蔽混凝土）的近期研究进展，并对关键性能进行了总结和比较。特别详细讨论了乏燃料领域研究和应用最为广泛的含硼不锈钢和碳化硼/铝复合中子吸收材料。讨论了用于乏燃料运输和储存的不同类型中子屏蔽材料在制备和应用中存在的问题及解决方案，并提出了它们的研究重点和发展趋势。