Using fast reactor component evaluation to pressurized water reactor life extension.
An understanding of the effects of long-term, low-dose-rate radiation on core components is critical to light-water reactor plant life extension. Following reactor shutdown, materials that had experienced long exposures to low-dose-rate irradiation were retrieved from the EBR-II research reactor for analysis. These components are being analyzed to provide insight into pressurized water reactor life extension. In this work, three examples of EBR-II materials analyses are highlighted: radiation-induced segregation in 304 stainless steel, stress relaxation in Inconel X750, and swelling in 316 stainless steel.;EVALUATION;FAST REACTORS;PWR TYPE REACTORS;
- Research Organization:
- Argonne National Lab. (ANL), Argonne, IL (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- DE-AC02-06CH11357
- OSTI ID:
- 942599
- Report Number(s):
- ANL/ED/CP-98990; JOMMER; TRN: US0903719
- Journal Information:
- JOM, Vol. 51, Issue 10 ; Oct. 1999; ISSN 1047-4838
- Country of Publication:
- United States
- Language:
- ENGLISH
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