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

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, B(4)C/Al composites, polymer-based composites, and shielding concrete) for transport...

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Detalles Bibliográficos
Autores principales: Qi, Zhengdong, Yang, Zhong, Li, Jianping, Guo, Yongchun, Yang, Guichun, Yu, Yang, Zhang, Jiachen
Formato: Online Artículo Texto
Lenguaje:English
Publicado: MDPI 2022
Materias:
Review
Acceso en línea:https://www.ncbi.nlm.nih.gov/pmc/articles/PMC9099936/
https://www.ncbi.nlm.nih.gov/pubmed/35591589
http://dx.doi.org/10.3390/ma15093255
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author Qi, Zhengdong
Yang, Zhong
Li, Jianping
Guo, Yongchun
Yang, Guichun
Yu, Yang
Zhang, Jiachen
author_facet Qi, Zhengdong
Yang, Zhong
Li, Jianping
Guo, Yongchun
Yang, Guichun
Yu, Yang
Zhang, Jiachen
author_sort Qi, Zhengdong
collection PubMed
description 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, B(4)C/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 B(4)C/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.
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spelling pubmed-90999362022-05-14 The Advancement of Neutron-Shielding Materials for the Transportation and Storage of Spent Nuclear Fuel Qi, Zhengdong Yang, Zhong Li, Jianping Guo, Yongchun Yang, Guichun Yu, Yang Zhang, Jiachen Materials (Basel) Review 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, B(4)C/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 B(4)C/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. MDPI 2022-04-30 /pmc/articles/PMC9099936/ /pubmed/35591589 http://dx.doi.org/10.3390/ma15093255 Text en © 2022 by the authors. https://creativecommons.org/licenses/by/4.0/Licensee MDPI, Basel, Switzerland. This article is an open access article distributed under the terms and conditions of the Creative Commons Attribution (CC BY) license (https://creativecommons.org/licenses/by/4.0/).
spellingShingle Review
Qi, Zhengdong
Yang, Zhong
Li, Jianping
Guo, Yongchun
Yang, Guichun
Yu, Yang
Zhang, Jiachen
The Advancement of Neutron-Shielding Materials for the Transportation and Storage of Spent Nuclear Fuel
title The Advancement of Neutron-Shielding Materials for the Transportation and Storage of Spent Nuclear Fuel
title_full The Advancement of Neutron-Shielding Materials for the Transportation and Storage of Spent Nuclear Fuel
title_fullStr The Advancement of Neutron-Shielding Materials for the Transportation and Storage of Spent Nuclear Fuel
title_full_unstemmed The Advancement of Neutron-Shielding Materials for the Transportation and Storage of Spent Nuclear Fuel
title_short The Advancement of Neutron-Shielding Materials for the Transportation and Storage of Spent Nuclear Fuel
title_sort advancement of neutron-shielding materials for the transportation and storage of spent nuclear fuel
topic Review
url https://www.ncbi.nlm.nih.gov/pmc/articles/PMC9099936/
https://www.ncbi.nlm.nih.gov/pubmed/35591589
http://dx.doi.org/10.3390/ma15093255
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