Simulation of stress corrosion crack growth in steam generator tubes-Reference-Cited by-同舟云学术

Simulation of stress corrosion crack growth in steam generator tubes

Published:2002-05 Issue:1-2 Volume:214 Page:91-101
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Shin Kyu In,Park Jai Hak,Kim Hong-Deok,Chung Han-Sub

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

Reference12 articles.

1. Bamford, W.H., Foster, J.P., 1995. Crack growth and microstructural characterization of alloy 600 head penetration materials, EPRI TR-105958.

2. Effect of hydrogen on the corrosion of steels in high temperature water;Berge;Corrosion,1976

3. Chung, H.S., Kim, K.T., Kim, H.D., Lee, H.J., Nam, M.W., 1998. A study on the integrity assessment of defected S/G tube, KEPRI Report.

4. Residual stresses in roller-expanded thin tubes;Druez;Exp. Mech.,1985

5. Frederick, G., Hernalsteen, P., Stubbe, J., Mcllree, A.R., 1987. Qualification of remedial methods to prevent primary-side stress corrosion cracking of steam generator tubing, EPRI NP-5249.

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