Advanced TEM characterization of stress corrosion cracking of Alloy 600 in pressurized water reactor primary water environment-Reference-Cited by-同舟云学术

Advanced TEM characterization of stress corrosion cracking of Alloy 600 in pressurized water reactor primary water environment

Published:2009-09 Issue:2 Volume:393 Page:254-266
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Sennour M.,Laghoutaris P.,Guerre C.,Molins R.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference15 articles.

1. Injection of vacancies at metal grain boundaries during the oxidation of nickel

2. Effect of the chromium content on the corrosion of nickel based alloys in primary water of pressurised nuclear reactors

3. Influence of oxide films on primary water stress corrosion cracking initiation of alloy 600

4. Hydrogen embrittlement of the Ni-base Alloy 600 correlated with hydrogen transport by dislocations

5. P.M. Scott, An overview of internal oxidation as a possible explanation of intergranular SCC of Alloy 600 in PWRS, in: Proceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-water Reactors, Newport Beach, CA, 1999, p. 3.

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