High-temperature flaw assessment procedure
- Oak Ridge National Lab., TN (United States)
- Central Research Inst. of Electric Power Industry, Tokyo (Japan)
- Nuclear Electric plc, Barnwood (UK)
Described is the background work performed jointly by the Electric Power Research Institute in the United States, the Central Research Institute of Electric Power Industry in Japan and Nuclear Electric plc in the United Kingdom with the purpose of developing a high-temperature flaw assessment procedure for reactor components. Existing creep-fatigue crack-growth models are reviewed, and the most promising methods are identified. Sources of material data are outlined, and results of the fundamental deformation and crack-growth tests are discussed. Results of subcritical crack-growth exploratory tests, creep-fatigue crack-growth tests under repeated thermal transient conditions, and exploratory failure tests are presented and contrasted with the analytical modeling. Crack-growth assessment methods are presented and applied to a typical liquid-metal reactor component. The research activities presented herein served as a foundation for the Flaw Assessment Guide for High-Temperature Reactor Components Subjected to Creep-Fatigue Loading published separately. 30 refs., 108 figs., 13 tabs.
- Research Organization:
- Electric Power Research Inst. (EPRI), Palo Alto, CA (United States); Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- EPRI; Electric Power Research Inst., Palo Alto, CA (United States)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6018121
- Report Number(s):
- ORNL-6677; ON: DE92000387
- Country of Publication:
- United States
- Language:
- English
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REACTOR COMPONENTS
THERMAL DEGRADATION
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DEFECTS
FRACTURE MECHANICS
STAINLESS STEEL-316
COORDINATED RESEARCH PROGRAMS
CRACK PROPAGATION
CRACKS
CREEP
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EPRI
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PROGRESS REPORT
THERMAL CYCLING
THERMAL SHOCK
THERMAL STRESSES
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ALLOYS
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AUSTENITIC STEELS
BREEDER REACTORS
CHROMIUM ALLOYS
CHROMIUM-NICKEL STEELS
CHROMIUM-NICKEL-MOLYBDENUM STEELS
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DEVELOPED COUNTRIES
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FAST REACTORS
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HEAT RESIS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HIGH ALLOY STEELS
IRON ALLOYS
IRON BASE ALLOYS
LIQUID METAL COOLED REACTORS
MATERIALS
MECHANICAL PROPERTIES
MECHANICS
MOLYBDENUM ALLOYS
NICKEL ALLOYS
REACTORS
RESEARCH PROGRAMS
STAINLESS STEELS
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