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Probabilistic analysis of initiation and early growth of stress corrosion cracks in BWR piping

Conference ·
OSTI ID:6744695
; ;
The purpose of this paper is to describe a probabilistic model of the initiation and early growth of stress corrosion cracks in sensitized 304 stainless steel weldments in boiling water reactor (BWR) piping. This treatment of crack initiation provides an extension of earlier models of reactor piping reliability which considered only the influence of pre-existing cracks. The inclusion of crack initiation is needed to provide agreement with field observations of cracking in BWR piping. A probabilistic treatment of this phenomenon is appropriate because of both the apparent randomness of observed field failures and the large scatter observed in related laboratory tests. The model is based on quantification of the scatter in laboratory observations once the influence of the major independent variables has been accounted for (stress level or strain rate, coolant oxygen level, temperature, and degree of sensitivity).
Research Organization:
Failure Analysis Associates, Palo Alto, CA
OSTI ID:
6744695
Report Number(s):
CONF-860722-
Country of Publication:
United States
Language:
English

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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360105 -- Metals & Alloys-- Corrosion & Erosion
ALLOYS
BWR TYPE REACTORS
CHEMICAL REACTIONS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
COOLING SYSTEMS
CORROSION
CORROSION RESISTANT ALLOYS
CRACK PROPAGATION
DYNAMIC LOADS
ENERGY SYSTEMS
FRACTURE MECHANICS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
JOINTS
MATERIALS
MATHEMATICAL MODELS
MECHANICS
MONTE CARLO METHOD
NICKEL ALLOYS
OPERATION
PIPES
PROBABILITY
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
RELIABILITY
SAFETY
STAINLESS STEEL-304
STAINLESS STEELS
STEADY-STATE CONDITIONS
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STRESS CORROSION
WATER COOLED REACTORS
WATER MODERATED REACTORS
WELDED JOINTS