Published 1993 | Version v1
Report Open

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

Description

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 ≤ a/T ≤ 0.9 with particular emphasis on shallow flaws (a/T ≤ 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

Availability note (English)

MF available from INIS under the Report Number; OSTI as DE93006206; NTIS; INIS; US Govt. Printing Office Dep.

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Additional details

Publishing Information

Imprint Pagination
20 p.
Report number
CONF-930702--4

Conference

Title
Pressure vessel and piping conference.
Dates
25-29 Jul 1993.
Place
Denver, CO (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
24059605
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DEFECTS; FINITE ELEMENT METHOD; FRACTURE MECHANICS; PRESSURE VESSELS; PWR TYPE REACTORS; STRESS INTENSITY FACTORS
Descriptors DEC
CALCULATION METHODS; CONTAINERS; ENRICHED URANIUM REACTORS; MECHANICS; NUMERICAL SOLUTION; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information