Progress and Considerations on Candidate Cladding Materials for Supercritical Water-Cooled Reactors

Zhang Lefu; Huang Tao; Su Haozhan; Gao Yang; Guo Xianglong; Shen Zhao; Chen Kai

doi:10.13832/j.jnpe.2025.01.0183

Volume 46 Issue 1

Feb. 2025

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Zhang Lefu, Huang Tao, Su Haozhan, Gao Yang, Guo Xianglong, Shen Zhao, Chen Kai. Progress and Considerations on Candidate Cladding Materials for Supercritical Water-Cooled Reactors[J]. Nuclear Power Engineering, 2025, 46(1): 183-190. doi: 10.13832/j.jnpe.2025.01.0183

Citation:

Zhang Lefu, Huang Tao, Su Haozhan, Gao Yang, Guo Xianglong, Shen Zhao, Chen Kai. Progress and Considerations on Candidate Cladding Materials for Supercritical Water-Cooled Reactors[J]. Nuclear Power Engineering, 2025, 46(1): 183-190. doi: 10.13832/j.jnpe.2025.01.0183

Citation:

Zhang Lefu, Huang Tao, Su Haozhan, Gao Yang, Guo Xianglong, Shen Zhao, Chen Kai. Progress and Considerations on Candidate Cladding Materials for Supercritical Water-Cooled Reactors[J]. Nuclear Power Engineering, 2025, 46(1): 183-190. doi: 10.13832/j.jnpe.2025.01.0183

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Progress and Considerations on Candidate Cladding Materials for Supercritical Water-Cooled Reactors

doi: 10.13832/j.jnpe.2025.01.0183

1.
School of Nuclear Science and Engineering, Shanghai Jiao Tong University, Shanghai, 200240, China
2.
China Institute of Atomic Energy, Beijing, 102413, China
3.
Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China
4.
School of Material Science and Engineering, Shanghai Jiao Tong University, Shanghai, 200240, China

Received Date: 2024-04-16
Rev Recd Date: 2024-12-11
Publish Date: 2025-02-15

Abstract

Abstract

The Supercritical Water-cooled Reactor (SCWR) is one of the six reactor types recommended by the Generation IV International Forum (GIF) due to its high thermal efficiency and simple structural design. This paper provides an overview of the design requirements and key performance challenges for SCWR cladding material, including the general corrosion, stress corrosion and irradiation properties of commercial candidate cladding materials that have been tested a lot. Ferrite/Martensite (F/M) steel, austenitic stainless steel and nickel-based alloy all have some performance deficiencies. Finally, the recent research progress of novel SCWR candidate cladding materials is reviewed, including alumina-forming austenitic (AFA) steels, oxide dispersion strengthened (ODS) steels, functionally gradient materials and microstructure improvement techniques.
- Supercritical Water-cooled Reactor,
- Fuel cladding material,
- General corrosion,
- Stress corrosion crack

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References(62)

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