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
 

Pressure vessel steel irradiation embrittlement formulas derived from PWR surveillance data

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5645782
None
Research Organization:
Westinghouse Electric Corporation, Hanford Engineering Development Laboratory, P.O. Box 1970, Richland, WA 99352
OSTI ID:
5645782
Report Number(s):
CONF-830609-
Conference Information:
Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 44
Country of Publication:
United States
Language:
English

Similar Records

Pressure-vessel-steel irradiation-embrittlement formulas derived for PWR surveillance data
Conference · Fri Dec 31 23:00:00 EST 1982 · OSTI ID:5956329
Statistical analysis of pressure vessel steel embrittlement data
Conference · Wed Jun 01 00:00:00 EDT 1983 · Trans. Am. Nucl. Soc.; (United States) · OSTI ID:5568457
A unified description of radiation embrittlement and annealing in pressure vessel steels
Conference · Fri Jun 01 00:00:00 EDT 1984 · Trans. Am. Nucl. Soc.; (United States) · OSTI ID:6648259

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
36 MATERIALS SCIENCE
360106 -- Metals & Alloys-- Radiation Effects
ALLOYS
CONTAINERS
CORRELATION FUNCTIONS
DAMAGING NEUTRON FLUENCE
EMBRITTLEMENT
FUNCTIONS
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION
LEAST SQUARE FIT
MATERIALS
MAXIMUM-LIKELIHOOD FIT
NEUTRON FLUENCE
NUMERICAL SOLUTION
PHYSICAL PROPERTIES
PHYSICAL RADIATION EFFECTS
PRESSURE VESSELS
PWR TYPE REACTORS
RADIATION EFFECTS
REACTOR MATERIALS
REACTORS
STEELS
THERMODYNAMIC PROPERTIES
TRANSITION TEMPERATURE
WATER COOLED REACTORS
WATER MODERATED REACTORS