Stress corrosion cracking of the AISI 316L stainless steel HAZ in a PWR nuclear reactor environment

Author:

Schvartzman Mônica Maria de Abreu Mendonça,Quinan Marco Antônio Dutra,Campos Wagner Reis da Costa,Lima Luciana Iglésias Lourenço

Publisher

Informa UK Limited

Subject

Metals and Alloys,Mechanical Engineering,Mechanics of Materials

Reference23 articles.

1. Simes S, Cleto J, Fortes P, Seixas J. Activities developed with the TIMES model at the New University of Lisbon. In: Gary Goldsteir, GianCarlo Tosato, editor. Global Energy Systems and Common Analyses – Final report of annex X (2005–2008). ETSAP - international energy agency implementing agreement for a programme of energy technology systems analysis. Ed. Gary Goldstein and GianCarlo Tosato; 2008

2. Scott PM. An overview of materials degradation by stress corrosion in PWRs. Eurocorr – Annual European corrosion conference of the European federation of corrosion, 12–16 September, Nice Acropolis; 2004

3. Alexandreanu B, Chen Y, Chopra KO, Chung MH, Gruber EE, Soppet KW, Shack JW. Environmentally assisted cracking in light water reactors. Argone National Laboratory – NUREG – CR-4667. US Regulatory Commission Office of Nuclear Regulatory Research, March 2007

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