Statistical analysis of pressure vessel steel embrittlement data
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5568457
None
- Research Organization:
- Oak Ridge National Laboratory, Oak Ridge, TN 37830
- OSTI ID:
- 5568457
- 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
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200* -- Nuclear Reactor Technology-- Components & Accessories
ALLOYS
CHARPY TEST
CONTAINERS
DAMAGING NEUTRON FLUENCE
DATA ANALYSIS
DESTRUCTIVE TESTING
EMBRITTLEMENT
IMPACT TESTS
IRON ALLOYS
IRON BASE ALLOYS
JOINTS
LEAST SQUARE FIT
MATERIALS
MATERIALS TESTING
MATHEMATICS
MAXIMUM-LIKELIHOOD FIT
MECHANICAL TESTS
NEUTRON FLUENCE
NUMERICAL SOLUTION
PHYSICAL PROPERTIES
PRESSURE VESSELS
REACTOR MATERIALS
STATISTICS
STEELS
TESTING
THERMODYNAMIC PROPERTIES
TRANSITION TEMPERATURE
WELDED JOINTS
220200* -- Nuclear Reactor Technology-- Components & Accessories
ALLOYS
CHARPY TEST
CONTAINERS
DAMAGING NEUTRON FLUENCE
DATA ANALYSIS
DESTRUCTIVE TESTING
EMBRITTLEMENT
IMPACT TESTS
IRON ALLOYS
IRON BASE ALLOYS
JOINTS
LEAST SQUARE FIT
MATERIALS
MATERIALS TESTING
MATHEMATICS
MAXIMUM-LIKELIHOOD FIT
MECHANICAL TESTS
NEUTRON FLUENCE
NUMERICAL SOLUTION
PHYSICAL PROPERTIES
PRESSURE VESSELS
REACTOR MATERIALS
STATISTICS
STEELS
TESTING
THERMODYNAMIC PROPERTIES
TRANSITION TEMPERATURE
WELDED JOINTS