Status of Knowledge of Radiation Embrittlement in USA Reactor Pressure Vessel Steels.
Abstract
Advances by experimental research in the USA toward an improved understanding of property changes in steel by elevated temperature ( approximately 288 deg C) irradiation are summarized. Four areas of investigation are reviewed including the confirmation and demonstration of guidelines for radiation resistant steels, the isolation of metallurgical factors contributing to variable radiation embrittlement sensitivity, the qualification of in situ heat treatments for periodic vessel embrittlement relief, and the correlation of notch ductility and fracture toughness changes with irradiation. Overall, the current state of the art provides both a high capability for tailoring steels for radiation service in new vessel construction and a promising method for controlling radiation embrittlement buildup in existing vessel construction. (Author)
Document Details
- Document Type
- Technical Report
- Publication Date
- Feb 01, 1982
- Accession Number
- ADA117973
Entities
People
- J. Russell Hawthorne
Organizations
- United States Naval Research Laboratory