Using fast reactor component evaluation for 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. For more information, contact T.R. Allen, Argonne National Laboratory-West, P.O. Box 2528, Idaho Falls, Idaho 83403-2528;(208)533-7760; fax (208) 533-7863; e-mail todd.allen@anlw.anl.gov.