Aging of reactor pressure vessels
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6558375
None
- Research Organization:
- Westinghouse Electric Corp., P.O. Box 2728, Pittsburgh, PA 15230
- OSTI ID:
- 6558375
- Report Number(s):
- CONF-840614-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 46
- Country of Publication:
- United States
- Language:
- English
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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
AGING
BARYONS
CONTAINERS
DAMAGING NEUTRON FLUENCE
ELEMENTARY PARTICLES
ELEMENTS
EMBRITTLEMENT
FERMIONS
FRACTURE MECHANICS
HADRONS
IRRADIATION
JOINTS
MECHANICAL PROPERTIES
MECHANICS
METALS
MONITORING
NATIONAL ORGANIZATIONS
NEUTRON FLUENCE
NEUTRONS
NUCLEONS
PHYSICAL RADIATION EFFECTS
POST-IRRADIATION EXAMINATION
PRESSURE VESSELS
PWR TYPE REACTORS
QUENCH AGING
RADIATION EFFECTS
REACTORS
STRESS INTENSITY FACTORS
TEMPERATURE EFFECTS
TENSILE PROPERTIES
THERMAL NEUTRONS
US NRC
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WELDED JOINTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
36 MATERIALS SCIENCE
360106 -- Metals & Alloys-- Radiation Effects
AGING
BARYONS
CONTAINERS
DAMAGING NEUTRON FLUENCE
ELEMENTARY PARTICLES
ELEMENTS
EMBRITTLEMENT
FERMIONS
FRACTURE MECHANICS
HADRONS
IRRADIATION
JOINTS
MECHANICAL PROPERTIES
MECHANICS
METALS
MONITORING
NATIONAL ORGANIZATIONS
NEUTRON FLUENCE
NEUTRONS
NUCLEONS
PHYSICAL RADIATION EFFECTS
POST-IRRADIATION EXAMINATION
PRESSURE VESSELS
PWR TYPE REACTORS
QUENCH AGING
RADIATION EFFECTS
REACTORS
STRESS INTENSITY FACTORS
TEMPERATURE EFFECTS
TENSILE PROPERTIES
THERMAL NEUTRONS
US NRC
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WELDED JOINTS