Recent trends in metallic fast reactor fuels research

被引：19

作者：

Aitkaliyeva, Assel ^{[1
]}

机构：

[1] Univ Florida, Dept Mat Sci & Engn, Dept Mate, 176 Rhines Hall, Gainesville, FL 32611 USA

来源：

JOURNAL OF NUCLEAR MATERIALS | 2022年 / 558卷

关键词：

Metallic fuels; Uranium-zirconium alloys; Uranium-plutonium-zirconium alloys; Irradiation behaviors; CLADDING CHEMICAL INTERACTION; U-ZR FUEL; POSTIRRADIATION EXAMINATION; ALLOYS; BEHAVIOR; ENERGY; MODEL; SB;

D O I：

10.1016/j.jnucmat.2021.153377

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

Metallic nuclear fuels have been extensively investigated for more than 60 years. Early studies noted that metallic fuels exhibit characteristic irradiation behaviors that set them apart from oxide fuels. By performing a critical review of historical data, the current gaps in the understanding of metallic U-Zr and U-Pu-Zr fuels (e.g., constituent redistribution, swelling and fission gas release) and recommendations for future research direction can be identified. This paper reviews and highlights the key aspects of the metallic fuel irradiation behaviors, with respect to the gaps in current understanding, based on the research performed in the past 3 years. (c) 2021 Elsevier B.V. All rights reserved.

引用

页数：7

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