Status of knowledge of radiation embrittlement in U. S. reactor pressure vessel steels
Advances in experimental research in the United States toward an improved understanding of property changes in steel by elevated temperature ( about 288/sup 0/ C) irradiation ar 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.
- Research Organization:
- Naval Research Laboratory, Washington, DC
- OSTI ID:
- 6489470
- Report Number(s):
- CONF-8110312-
- Journal Information:
- Am. Soc. Test. Mater., Spec. Tech. Publ.; (United States), Vol. STP 819; Conference: Meeting on nuclear technology and applications, Vienna, Austria, 19 Oct 1981
- Country of Publication:
- United States
- Language:
- English
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Status of knowledge of radiation embrittlement in USA reactor pressure vessel steels
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
PRESSURE VESSELS
EMBRITTLEMENT
PHYSICAL RADIATION EFFECTS
STEELS
DUCTILITY
FRACTURE PROPERTIES
HEAT TREATMENTS
MATERIALS TESTING
METALLURGICAL EFFECTS
TEMPERATURE EFFECTS
ALLOYS
CONTAINERS
IRON ALLOYS
IRON BASE ALLOYS
MECHANICAL PROPERTIES
RADIATION EFFECTS
TENSILE PROPERTIES
TESTING
360106* - Metals & Alloys- Radiation Effects
220200 - Nuclear Reactor Technology- Components & Accessories