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

Развитие материалов для нейтронной защиты при хранении отработавшего ядерного топлива
Xuelong Fu, Zhengbo Ji, Wei Lin, Yunfeng Yu, Tao Wu
2021-05-07

boron carbide (B4C)high-density concreteneutron shielding materialspolymer compositesspent nuclear fuel
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.
1
Advances in neutron shielding materials are driven by irradiation conditions in the nuclear industry and the need to protect facilities and personnel from spent-fuel radiation.
2
Elemental composition, density, thermal properties, and mechanical properties are identified as key criteria for comparing neutron shielding materials.
3
Neutron shielding composites for spent nuclear fuel storage convert fast neutrons into thermal neutrons that can be absorbed by elements with high macroscopic cross sections.
4
Recent material development emphasizes additives including boron carbide, boron nitride, boric acid, and colemanite.
5
The review compares multiple shielding categories, including metal-matrix alloys, polymer composites, high-density concrete, heavy metals, paraffin, and other boron-containing composites.

neutron shielding materials for the storage of spent nuclear fuel

their composition, density, thermal and mechanical properties, and neutron moderation and absorption performance

Publication Details
Publication Date
2021-05-07
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Authors
Xuelong Fu
Zhengbo Ji
Wei Lin
Yunfeng Yu
Tao Wu
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