Critical experiments, measurements and analyses to establish a crack arrest methodology for nuclear pressure vessel steels
Technical Report
·
OSTI ID:6207602
Results of a program seeking (i) dynamic analyses of crack arrest in thermally stressed nuclear pressure vessels, (ii) standardization of a laboratory test method for measuring the crack arrest toughness, and (iii) a crack arrest toughness data base for unirradiated and irradiated nuclear steels and weldments are summarized.
- Research Organization:
- Battelle Columbus Labs., OH (USA)
- OSTI ID:
- 6207602
- Report Number(s):
- NUREG/CR-0825; BMI-2025
- Country of Publication:
- United States
- Language:
- English
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Critical experiments, measurements, and analyses to establish a crack arrest methodology for nuclear pressure vessel steels
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
ALLOYS
CARBON STEELS
CONTAINERS
CRACKS
DATA
DATA COMPILATION
FRACTURE PROPERTIES
INFORMATION
IRON ALLOYS
IRON BASE ALLOYS
JOINTS
MATERIALS TESTING
MECHANICAL PROPERTIES
MECHANICAL TESTS
NUMERICAL DATA
POWER REACTORS
PRESSURE VESSELS
RADIATION EFFECTS
REACTORS
RESEARCH PROGRAMS
SIMULATION
STEEL-ASTM-A508
STEEL-ASTM-A533-B
STEELS
STRESSES
TESTING
THERMAL STRESSES
TWO-DIMENSIONAL CALCULATIONS
WELDED JOINTS
220900* -- Nuclear Reactor Technology-- Reactor Safety
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
ALLOYS
CARBON STEELS
CONTAINERS
CRACKS
DATA
DATA COMPILATION
FRACTURE PROPERTIES
INFORMATION
IRON ALLOYS
IRON BASE ALLOYS
JOINTS
MATERIALS TESTING
MECHANICAL PROPERTIES
MECHANICAL TESTS
NUMERICAL DATA
POWER REACTORS
PRESSURE VESSELS
RADIATION EFFECTS
REACTORS
RESEARCH PROGRAMS
SIMULATION
STEEL-ASTM-A508
STEEL-ASTM-A533-B
STEELS
STRESSES
TESTING
THERMAL STRESSES
TWO-DIMENSIONAL CALCULATIONS
WELDED JOINTS