Corrosion behavior of Alloy 690 in aerated supercritical water

Author:

Zhong Xiangyu,Han En-Hou,Wu Xinqiang

Funder

National Basic Research Program of China

National Science and Technology Major Project

Innovation Fund of Institute of Metal Research (IMR)

Chinese Academy of Sciences (CAS)

Publisher

Elsevier BV

Subject

General Materials Science,General Chemical Engineering,General Chemistry

Reference47 articles.

1. A Technology Roadmap for Generation IV Nuclear Energy Systems, in: US DOE Nuclear Energy Research Advisory Committee and the Generation IV International Forum (GIF-002-00), 2002.

2. Generation IV roadmap R&D scope report for water cooled reactor systems, in: US DOE Nuclear Energy Research Advisory Committee and the Generation IV International Forum (GIF-003-00), 2002.

3. Corrosion in high-temperature and supercritical water and aqueous solutions: a review;Kritzer;J. Supercrit. Fluid.,2004

4. Progress in corrosion resistant materials for supercritical water reactors;Sun;Corros. Sci.,2009

5. G.S. Was, S. Teysseyre, Challenges and recent progress in corrosion and stress corrosion cracking of alloys for supercritical water reactor core components, in: 12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Minerals, Metals and Materials Society, Salt Lake City, UT, United states, 2005, pp. 1343–1357.

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