Study on reducing the risk of stress corrosion cracking of austenitic stainless steel hydraulically expanded joints

Author:

Hong Ying,Wang Xuesheng,Wang Yan,Zhang Zhao

Funder

Key Research Program of Science and Technology Commission of Shanghai Municipality

Publisher

Elsevier BV

Subject

General Engineering,General Materials Science

Reference14 articles.

1. AFCEN, RCC-M-2007 Design and Construction Rules for Mechanical Components of PWR Nuclear Islands.

2. Overview of steam generator tube degradation and integrity issues;Diercks;Nucl. Eng. Des.,1999

3. Propagation of stress corrosion cracks in steam generator tubes;Cizelj;Int. J. Pres. Ves. Pip.,1995

4. Estimation of residual stresses in hydraulically expanded tube-to-tubesheet joints;Allam;J. Pres. Ves. Technol.,1998

5. Residual Stresses in Transition Zones of Heat Exchanger Tubes;Updike;J. Pres. Ves. Technol.,1992

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