Corrosion-fatigue crack-growth rates in austenitic stainless steels in light water reactor environments-Reference-Cited by-同舟云学术

Corrosion-fatigue crack-growth rates in austenitic stainless steels in light water reactor environments

Published:1988-01 Issue:1 Volume:31 Page:55-68
ISSN:0308-0161
Container-title:International Journal of Pressure Vessels and Piping
language:en
Short-container-title:International Journal of Pressure Vessels and Piping

Author:

Gilman J.D.,Rungta R.,Hinds P.,Mindlin H.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Mechanics of Materials,General Materials Science

Reference18 articles.

1. Environmentally-controlled cracking of stainless and low-alloy steels in light-water reactor environments;Ford;Electric Power Research Institute Report NP-5064M, Palo Alto, CA,1986

2. A new parameter for characterizing corrosion fatigue crack growth;Shoji;J. Eng. Mater. Technol.,1981

3. Role of loading variables in environment enhanced crack growth of water-cooled nuclear reactor pressure vessel steels;Shoji,1983

4. EPRI database for environmentally-assisted cracking (EDEAC);Mindlin;Electric Power Research Institute Report NP-4485,1986

5. Fatigue crack growth correlation for austenitic stainless steels in air;James,1985

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