Stress-intensity-factor influence coefficients for axial and circumferential flaws in reactor pressure vessels

Conference · Thu Dec 31 23:00:00 EST 1992

OSTI ID:6633744

Bryson, J W; Dickson, T L

Weight-function techniques in linear elastic fracture mechanics utilize stress-intensity-factor influence coefficients K* and superposition principles to compute stress intensity factors. This paper presents influence coefficients for two flaw geometries often employed in fracture analyses of reactor pressure vessels: (1) infinitely long, axial, inside-surface flaws and (2) 360[degrees], circumferential, inside-surface flaws. Calculations were performed using ABAQUS, a nuclear quality assurance (NQA-1) certified finite-element program which employs a highly accurate crack extension technique for the computation of theJ-integral. Influence coefficients are computed for flaw depths in the range 0.01 [le] a/T [le] 0.9 with particular emphasis on shallow flaws (a/T [le] 0. 1). This study addresses vessels having R/T = 10 which is appropriate for most PWRs in USA. The influence coefficients have been implemented in the FAVOR fracture-mechanics code currently being developed under the NRC-funded HSST Program at ORNL.

• Research Organization: Oak Ridge National Lab., TN (United States)
• Sponsoring Organization: NRC; Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 6633744
• Report Number(s): CONF-930702-4; ON: DE93006206
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
CALCULATION METHODS
CONTAINERS
DEFECTS
ENRICHED URANIUM REACTORS
FINITE ELEMENT METHOD
FRACTURE MECHANICS
MECHANICS
NUMERICAL SOLUTION
POWER REACTORS
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PWR TYPE REACTORS
REACTORS
STRESS INTENSITY FACTORS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS