Material research for the supercritical water-cooled reactor—summary and open issues-Reference-Cited by-同舟云学术

Material research for the supercritical water-cooled reactor—summary and open issues

Published:2020 Issue: Volume: Page:403-435
ISSN:
Container-title:Nuclear Corrosion
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Author:

Novotny Radek,Guzonas David

Publisher

Elsevier

Reference108 articles.

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2. A. Chukwudi, M. Edwards, M. Gaudet, D. Guzonas, H. Hamilton, X. Huang, Canadian super-critical water-cooled reactor concept—research and development, CNL Report 217-120000-440, 2014.

3. L. Walters, M. Wright, D. Guzonas, Irradiation issues and material selection for Canadian SCWR components, in: 8th International Symposium on Super-critical Water-cooled Reactors”, 13–15 March 2017, Chengdu, China, 2017.

4. Materials for high performance light water reactors;Erlich;J. Nucl. Mater.,2004

5. R.J. Klassen, H. Rajakumar, Combined effect of irradiation and temperature on the mechanical strength of inconel 800H and AISI 310 alloys for in-core components of a GEN-IV SCWR, in: 7th International Symposium on Supercritical Water-Cooled Reactors (ISSCWR7), Helsinki, 15–18 March 2015, paper ISSCWR7-2006, 2015.

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