Published September 1994 | Version v1
Journal article

Irradiation-assisted stress corrosion cracking

  • 1. Metals and Ceramics Division, Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 37831 (United States)
  • 2. Pacific Northwest Laboratories, P.O. Box 999, Richland, WA 99352 (United States)
  • 3. M.J. Schiff and Associates, Claremont, CA 91711 (United States)

Description

Irradiation-assisted stress corrosion cracking (IASCC) is a concern for both stainless steel and high nickel austenitic alloys irradiated in aqueous environments. A large experience base is available for conventional austenitic alloys from both commercial and experimental fission reactors. The current understanding of IASCC is reviewed with reference to recent experimental and theoretical results. Possible effects of fusion relevant irradiation conditions on IASCC will be discussed along with results from mixed spectrum reactor irradiations selected to approximate the fusion reactor environment. ((orig.))

Additional details

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
212-215
Journal Issue
pt.A
Journal Page Range
p. 52-59.
ISSN
0022-3115
CODEN
JNUMAM

Conference

Title
6. international conference on fusion reactor materials (ICFRM-6).
Dates
27 Sep - 1 Oct 1993.
Place
Stresa (Italy).