Skip to main content
OSTI.GOVU.S. Department of Energy Office of Scientific and Technical Information
U.S. Department of Energy
Office of Scientific and Technical Information
 

Radiation embrittlement of nuclear reactor pressure vessel steels: An international review

Conference ·
OSTI ID:7046770
This book presents papers on radiation embrittlement of nuclear reactor pressure vessel steels. Topics covered include the following: the effect of Irradiation on the elasto-plastic toughness of pressure; boiling water reactor (BWR) pressure vessel surveillance program; and annealing and reirradiation response of irradiated pressure vessel steels.
OSTI ID:
7046770
Report Number(s):
CONF-8410457-
Country of Publication:
United States
Language:
English

Similar Records

Radiation embrittlement of Spanish nuclear reactor pressure vessel steels
Book · Tue Nov 30 23:00:00 EST 1993 · OSTI ID:139990
Irradiation embrittlement of pressure vessel steels: A review of activities in France
Conference · Thu Oct 01 00:00:00 EDT 1981 · Am. Soc. Test. Mater., Spec. Tech. Publ.; (United States) · OSTI ID:6475131
Radiation embrittlement of nuclear reactor pressure vessel steels: An international review (second volume)
Book · Tue Dec 31 23:00:00 EST 1985 · OSTI ID:5492106

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
36 MATERIALS SCIENCE
360106 -- Metals & Alloys-- Radiation Effects
ABSTRACTS
ALLOYS
ANNEALING
BWR TYPE REACTORS
CONTAINERS
DESTRUCTIVE TESTING
DOCUMENT TYPES
ELASTICITY
FRACTURE PROPERTIES
HEAT TREATMENTS
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION
LEADING ABSTRACT
MATERIALS
MATERIALS TESTING
MECHANICAL PROPERTIES
MEETINGS
MONITORING
PHYSICAL RADIATION EFFECTS
PLASTICITY
PRESSURE VESSELS
RADIATION EFFECTS
REACTOR MATERIALS
REACTORS
STEELS
TENSILE PROPERTIES
TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS