Approximate evaluation method for ductile fracture analysis of circumferentially through-wall-cracked pipe subjected to combined bending and tension
Creators
- 1. Materials Science Department, Central Research Institute of Electric Power Industry, Komae, Tokyo (Japan)
Description
To estimate the structural integrity of the Light Water Reactor piping, combined loading consists of tensile load due to internal pressure and bending load under seismic condition should be considered as a basic loading mode. However, theoretical investigation on the methodology to evaluate ductile fracture behavior is not adequate to date. In this study, an approximate evaluation method for ductile fracture analysis of circumferentially through-wall-cracked pipe subjected to combined bending and tension was newly developed. This method can explicitly incorporate the contribution of both tension and bending. The effect of growing crack is also considered in the method. This method was then applied to the full-scale pipe fracture tests. Based on the comparison with experimental results as well as finite element calculations, it could be ascertained that the proposed method could well predict ductile fracture behavior under combined loading. The effect of combined loading on ductile fracture was sensitivity-studied using the proposed method. As a result, it was quantitatively found that the superposition of internal pressure reduced the maximum load of cracked pipe. (author)
Additional details
Publishing Information
- Publisher
- The Japan Welding Engineering Society
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- 2nd international workshop on the integrity of nuclear components
- Imprint Pagination
- 289 p.
- Journal Page Range
- p. 209-228
Conference
- Title
- 2. international workshop on the integrity of nuclear components
- Dates
- 20-21 Apr 1998
- Place
- Tokyo (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 30030183
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ANALYTICAL SOLUTION; ASYMPTOTIC SOLUTIONS; BENDING; CRACK PROPAGATION; CRACKS; DUCTILITY; FRACTURE MECHANICS; FRACTURES; HIGH PRESSURE; PIPES; PWR TYPE REACTORS
- Descriptors DEC
- DEFORMATION; ENRICHED URANIUM REACTORS; FAILURES; MECHANICAL PROPERTIES; MECHANICS; POWER REACTORS; REACTORS; TENSILE PROPERTIES; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS