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Cracking behavior of thermally aged and irradiated CF-8 cast austenitic stainless steel

  • Published:2015-11 Issue: Volume:466 Page:560-568
  • ISSN:0022-3115
  • Container-title:Journal of Nuclear Materials
  • language:en
  • Short-container-title:Journal of Nuclear Materials

Author:

Chen Y.,Alexandreanu B.,Chen W.-Y.ORCID,Natesan K.,Li Z.,Yang Y.,Rao A.S.

Funder

U.S. Nuclear Regulatory Commission

U.S. Department of Energy

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference26 articles.

1. Expert Panel Report on Proactive Materials Degradation Assessment;U.S. NRC,2006

2. Initial Assessment of the Mechanisms and Significance of Low-Temperature Embrittlement of Cast Stainless Steels in LWR Systems;Chopra,1990

3. Estimation of Fracture Toughness of Cast Stainless Steels During Thermal Aging in LWR Systems;Chopra,1994

4. Ferrite measurement and control in cast duplex stainless steel;Aubrey,1982
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