Critical experiments, measurements and analyses to establish a crack arrest methodology for nuclear pressure vessel steels. Quarterly report, April--June 1978
Technical Report
·
OSTI ID:6322724
Results of a program seeking (i) dynamc 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 described. The dynamic analysis is used to examine a hypothetical run-arrest event in a thermally stressed cylinder for the conditions of the Oak Ridge National Laboratory Thermal Shock Experiment TSE-4 and an assumed brittle material. A large crack jump amounting to 69% of the remaining cylinder wall is calculated. A statistical analysis of the crack arrest toughness measurements on unirradiated test pieces is presented.
- Research Organization:
- Battelle Columbus Labs., OH (USA)
- OSTI ID:
- 6322724
- Report Number(s):
- NUREG/CR-0652; BMI-2018
- 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
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
ALLOYS
CARBON STEELS
CONTAINERS
CRACKS
FRACTURE PROPERTIES
IRON ALLOYS
IRON BASE ALLOYS
MECHANICAL PROPERTIES
PRESSURE VESSELS
REACTOR COMPONENTS
RESEARCH PROGRAMS
STEEL-ASTM-A508
STEEL-ASTM-A533-B
STEELS
TESTING
220200* -- Nuclear Reactor Technology-- Components & Accessories
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
ALLOYS
CARBON STEELS
CONTAINERS
CRACKS
FRACTURE PROPERTIES
IRON ALLOYS
IRON BASE ALLOYS
MECHANICAL PROPERTIES
PRESSURE VESSELS
REACTOR COMPONENTS
RESEARCH PROGRAMS
STEEL-ASTM-A508
STEEL-ASTM-A533-B
STEELS
TESTING