Journal ArticleDOI
Stress Corrosion Crack Growth in Type 316 Stainless Steel in Supercritical Water
TLDR
In this article, a crack growth rate test on a compact tension specimen of Type 316 (UNS S31600) stainless steel was conducted in pure water under both subcritical and supercritical conditions.Abstract:
A crack growth rate test on a compact tension specimen of Type 316 (UNS S31600) stainless steel was conducted in pure water under both subcritical and supercritical conditions. The crack g...read more
Citations
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Journal ArticleDOI
On the stress corrosion crack growth behaviour in high temperature water of 316L stainless steel made by laser powder bed fusion additive manufacturing
TL;DR: In this article, a comprehensive study of the stress corrosion crack growth behavior of laser additively-manufactured (AM) 316L stainless steel in high temperature water was performed and a wide range of parameters and their effects were evaluated, including microstructure, heat treatment, stress intensity factor, cold work, crack orientation, oxidizing vs. reducing conditions, and porosity.
Journal ArticleDOI
Overview on corrosion in supercritical fluids
Stéphane Sarrade,Damien Féron,Fabien Rouillard,Stephane Perrin,Raphaël Robin,Jean-Christophe Ruiz,Hubert-Alexandre Turc +6 more
TL;DR: In this paper, an overview on the corrosion behavior of metallic metals and alloys under pressure and temperature conditions appropriate for supercritical fluids is carried out, highlighting how SCW density changes the corrosion mechanisms.
Journal ArticleDOI
The Slow Strain Rate Stress Corrosion Cracking Test—A 50 Year Retrospective
TL;DR: The slow strain rate test (SSRT) as mentioned in this paper has been widely used in research for sour service, buried natural gas pipelines, ethanol transportation, nuclear power, low pressure turbines, and mechanism studies.
Journal ArticleDOI
Supercritical water-cooled reactor materials – Summary of research and open issues
D. Guzonas,R. Novotny +1 more
TL;DR: In this paper, the materials requirements of various supercritical water-cooled nuclear power plants are introduced, with a focus on the European Union pressure vessel concept and the Canadian pressure tube concept.
Book ChapterDOI
Material Performance in Supercritical Water
TL;DR: The Supercritical Water-Cooled Reactor (SCWR) design has been selected as one of the Generation IV reactor concepts because of its higher thermal efficiency and plant simplification compared to current light water reactors (LWRs) as mentioned in this paper.
References
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Journal Article
Stress Corrosion Crack Growth Rate Behavior of Various Grades of Cold Worked Stainless Steel in High Temperature Water
Journal ArticleDOI
Principles and Procedures Employed in Design and Interpretation of Atmospheric Corrosion Tests
TL;DR: The principles under which atmospheric corrosion tests are made are much the same as those applicable to other types of testing, such as accelerated tests, specimen size, location of test sites, differences in atmospheres, difference in metals and influence of alloying constituents as discussed by the authors.
Challenges and recent progress in corrosion and stress corosion cracking of alloys for supercritical water reactor core components
G. S. Was,S. Teysseyre +1 more
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