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Fatigue crack growth behavior of reactor pressure vessel steels in air and high-temperature water environments

  • Published:2008-11 Issue:11 Volume:85 Page:772-781
  • 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:

Huang J.Y.,Yeh J.J.,Kuo R.C.,Jeng S.L.,Young M.C.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Mechanics of Materials,General Materials Science

Reference25 articles.

1. Aging and life extension of major light water reactor components;Shah,1993

2. Microstructural evaluation of fatigue damage in SA533-B1 and type 316L stainless steels;Chen;J Mater Sci,2003

3. Performance and evaluation of light water reactor pressure vessels;Van Der Sluys,1987

4. Performance and evaluation of light water reactor pressure vessels;O'Donnell,1995

5. Performance and evaluation of light water reactor pressure vessels;Stahlkopf,1987

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