Lifetime estimation of a BWR core shroud in terms of IGSCC-Reference-Cited by-同舟云学术

Lifetime estimation of a BWR core shroud in terms of IGSCC

Published:2020-11 Issue: Volume:368 Page:110831
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Balachov Iouri,Fekete Balazs,Macdonald Digby D.,Spencer Benjamin^ORCID

Funder

U.S. Department of Energy

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference45 articles.

1. Stress Corrosion Cracking in Light Water Reactors: Good Practices and Lessons Learned. — Vienna: International Atomic Energy Agency, 2011.

2. BWRVIP Vessel and Internals Project Update, Drew Odell, Exelon, BWRVIP Integration Committee Technical Chairman EPRI-NRC Technical Exchange Meetings, May 22-25, 2017.

3. Status Report: Intergranular Stress Corrosion Cracking of BWR Core Shrouds and Other Internal Components, NUREG-1544, 1996.

4. J.K. McKinley, W. H. Bamford, A. M. Ruminski, T. L. Meikle, J. L. McFadden, “Comparison of Boiling Water Reactor and Pressurized Water Reactor Experience with Cracking of Austenitic Stainless Steel”, Enclosure 3 to MRP 2018-011, Westinghouse Electric Company, 2018.

5. A. Roth, “Review of Intergranular Cracking in Austenitic Stainless Steel Components of BWR RPV-Internals,” Fontevraud 8, Avignon, France, September 15-18, 2014.

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