A review of irradiation effects on LWR core internal materials – IASCC susceptibility and crack growth rates of austenitic stainless steels

Author:

Chopra O.K.,Rao A.S.

Publisher

Elsevier BV

Subject

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

Reference68 articles.

1. EPRI TR-107159;Bruemmer,1996

2. A review of irradiation assisted stress corrosion cracking

3. P. L. Andresen, F.P. Ford, S.M. Murphy, J.M. Perks, in: Proc. 4th Intl. Symp. on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, NACE, Houston, TX, 1990, pp. 1.83–1.121.

4. G.S. Was, P.L. Andresen, Corrosion, vol. 63, Paper No. 1, NACE, Houston, TX, 2007.

5. K.S. Brown, G.M. Gordon, in: Proc. Third Intl. Symp. on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactor, Metallurgical Society, Warrendale, PA, 1987, pp. 243–248.

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