Current research on environmentally assisted cracking in light water reactor environments-Reference-Cited by-同舟云学术

Current research on environmentally assisted cracking in light water reactor environments

Published:1999-12 Issue:2-3 Volume:194 Page:205-223
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Chopra O.K,Chung H.M,Kassner T.F,Park J.H,Shack W.J,Zhang J,Brust F.W,Dong P

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

Reference38 articles.

1. An analysis of the effects of sulfur content and potential on corrosion fatigue crack growth in reactor pressure vessel steels;Atkinson;Corros. Sci.,1996

2. A constitutive model for welding process simulation using finite element methods;Brust,1997

3. Brust, F.W., Dong, P., Zhang, J., 1997b. Crack growth behavior in residual stress fields of a core shroud girth weld. In: Mehta, H.S., (Ed.), Fracture and Fatigue, PVP-Vol. 350, American Society of Mechanical Engineers, New York, pp. 391–406.

4. A review of the fatigue crack extension behaviour of ferritic reactor pressure vessels materials in pressurized water reactor environments;Bulloch;Res. Mech.,1989

5. Effects of LWR environments on fatigue life of carbon and low-alloy steels;Chopra,1995

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