The cracking growth behavior of a sensitized Alloy 800H in supercritical water

Author:

Su HaozhanORCID,Huang Tao,Wang Jiamei,Zhang Lefu,Chen Kai

Funder

National Key Research and Development Program of China

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference48 articles.

1. A Technology Roadmap for Generation IV Nuclear Energy Systems. U.S. DOE Nuclear Energy Research Advisory Committee and the Generation IV International Forum 2002.

2. Waterside corrosion of M5 alloy in lithiated/borated and supercritical water: influences of aqueous environments;Jiang;J. Supercrit. Fluids,2023

3. Corrosion behavior and mechanisms of Al2O3 and Mo coated Zircaloy-4 in high-temperature lithiated water;Jiang;Corros. Sci.,2022

4. Materials and Water Chemistry for Supercritical Water-Cooled Reactors;Guzonas,2018

5. Effect of temperature and dissolved oxygen on stress corrosion cracking behavior of P92 ferritic-martensitic steel in supercritical water environment;Zhang;J. Nucl. Mater.,2018

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