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Journal: Materials, 2022
Volume: 15
Number: 3255

Article: The Advancement of Neutron-Shielding Materials for the Transportation and Storage of Spent Nuclear Fuel
Authors: by Zhengdong Qi, Zhong Yang, Jianping Li, Yongchun Guo, Guichun Yang, Yang Yu and Jiachen Zhang
Link: https://www.mdpi.com/1996-1944/15/9/3255

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