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U.S. Department of Energy
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Segregation in a neutron-irradiated type 316 stainless steel

Conference ·
OSTI ID:5246524
 [1];  [2]
  1. Oak Ridge National Lab., TN (United States)
  2. Westinghouse Electric Corp., Pittsburgh, PA (United States). Science and Technology Center

Radiation-induced segregation (RIS) and associated irradiation- assisted stress corrosion cracking (IASCC) of austenitic alloys may be a major factor in limiting component lifetimes in water-cooled nuclear reactors. There are some similarities between radiation- induced sensitization/IASCC and thermally-induced sensitization/intergranular stress corrosion cracking. Both processes are associated with chromium depletion at grain boundaries. Segregation to boundaries in a neutron irradiated type 316 stainless steel has been investigated with both energy-dispersive X-ray spectrometry (EDXS) and parallel detection electron energy loss spectrometry (PEELS). This report discusses work on segregation in a neutron-irradiated SS-316 sample.

Research Organization:
Oak Ridge National Lab., TN (United States)
Sponsoring Organization:
DOE; USDOE, Washington, DC (United States)
DOE Contract Number:
AC05-84OR21400; AC05-76OR00033
OSTI ID:
5246524
Report Number(s):
CONF-920819-10; ON: DE92011039
Country of Publication:
United States
Language:
English