Residual stress analysis in reactor pressure vessel attachments

Technical Report · Thu Aug 01 04:00:00 EDT 1991

OSTI ID:6239585

Dexter, R J ^[1]; Pont, D ^[2]

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1. Southwest Research Inst., San Antonio, TX (United States)
2. FRAMASOFT+CSI, 69 - Lyon (France)

Residual stresses in cladding and welded attachments could contribute to the problem of stress-corrosion cracking in boiling-water reactors (BWR). As part of a larger program aimed at quantifying residual stress in BWR components, models that would be applicable for predicting residual stress in BWR components are reviewed and documented. The review includes simple methods of estimating residual stresses as well as advanced finite-element software. In general, simple methods are capable of predicting peak magnitudes of residual stresses but are incapable of adequately characterizing the distribution of residual stresses. Ten groups of researchers using finite-element software are reviewed in detail. For each group, the assumptions of the model, possible simplifications, material property data, and specific applications are discussed. The most accurate results are obtained when a metallurgical simulation is performed, transformation plasticity effects are included, and the heating and cooling parts of the welding thermal cycle are simulated. Two models are identified which can provide these features. The present state of these models and the material property data available in the literature are adequate to quantify residual stress in BWR components.

• Research Organization: Electric Power Research Inst., Palo Alto, CA (United States); Southwest Research Inst., San Antonio, TX (United States)
• Sponsoring Organization: EPRI; Electric Power Research Inst., Palo Alto, CA (United States)
• OSTI ID: 6239585
• Report Number(s): EPRI-NP-7469
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
A CODES
B CODES
BWR TYPE REACTORS
CHEMICAL REACTIONS
COMPUTER CODES
COMPUTERIZED SIMULATION
CONTAINERS
CORROSION
CRACKS
ENRICHED URANIUM REACTORS
FABRICATION
FINITE ELEMENT METHOD
JOINING
JOINTS
MECHANICAL PROPERTIES
NUMERICAL SOLUTION
POWER REACTORS
PRESSURE VESSELS
REACTOR COMPONENTS
REACTORS
S CODES
SIMULATION
STRESS ANALYSIS
STRESS CORROSION
STRESSES
THERMAL ANALYSIS
THERMAL CYCLING
THERMAL REACTORS
W CODES
WATER COOLED REACTORS
WATER MODERATED REACTORS
WELDED JOINTS
WELDING