Analysis of crack initiation and growth in the high level vibration test at Tadotsu
A High Level Vibration Test (HLVT) Program was carried out recently on the seismic table at the Tadotsu Engineering Laboratory of Nuclear Power Engineering Center (NUPEC) in Japan. The objective of the study being performed at Brookhaven National Laboratory is to use the HLVT data to assess the accuracy and usefulness of existing methods for predicting crack initiation and growth under complex, large amplitude loading. The work to be performed as part of this effort involves: (1) analysis of the stress/strain distribution in the vicinity of the crack, including the potential for residual stresses due to the weld repair; (2) analysis of the number of load cycles required for crack initiation, including estimates of the impact of the weld repair on the crack initiation behavior; (3) analysis of crack advance as a function of applied loading (classic fatigue versus cyclic tearing) taking into account the variable amplitude loading and the possible influence of the repair; and (4) material property testing to supplement the work performed as part of the HLVT, providing the materials data necessary to perform the analysis efforts. A summary of research progress for FY 1990 is presented. 2 refs.
- Research Organization:
- Brookhaven National Lab. (BNL), Upton, NY (United States)
- Sponsoring Organization:
- USNRC; Nuclear Regulatory Commission, Washington, DC (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 5905789
- Report Number(s):
- BNL-NUREG-45855; ON: DE91009481; TRN: 91-010378
- Country of Publication:
- United States
- Language:
- English
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PRIMARY COOLANT CIRCUITS
CRACK PROPAGATION
SEISMIC EFFECTS
PWR TYPE REACTORS
STAINLESS STEELS
BNL
CRACKS
DEFORMATION
EARTHQUAKES
FATIGUE
JAPAN
MECHANICAL VIBRATIONS
MICROSTRUCTURE
PLASTICITY
PRESSURE VESSELS
REACTOR COMPONENTS
REACTOR MATERIALS
RESEARCH PROGRAMS
SCALE MODELS
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WELDED JOINTS
ALLOYS
ASIA
CONTAINERS
COOLING SYSTEMS
CRYSTAL STRUCTURE
ELECTRON MICROSCOPY
ENERGY SYSTEMS
HIGH ALLOY STEELS
IRON ALLOYS
IRON BASE ALLOYS
JOINTS
MATERIALS
MECHANICAL PROPERTIES
MICROSCOPY
NATIONAL ORGANIZATIONS
REACTOR COOLING SYSTEMS
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SEISMIC EVENTS
STEELS
STRUCTURAL MODELS
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US DOE
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220900* - Nuclear Reactor Technology- Reactor Safety
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Light-Water Moderated
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360103 - Metals & Alloys- Mechanical Properties