The proposal of crack growth evaluation method for piping under seismic loading
- 1. Japan Atomic Energy Agency (JAEA), Nuclear Safety Research Center, Tokai, Ibaraki (Japan)
- 2. Japan Nuclear Energy Safety Organization (JNES), Tokyo (Japan)
Description
In this study, an effect of excessive tensile and compressive loading on the crack growth behavior of piping has been evaluated through cracked plate testing. It was observed that excessive loading had changed crack growth rate. Effect on the crack growth behavior of excessive load was evaluated focusing on a crack blunting and a stress distribution near the crack tip. The crack growth evaluation method under seismic loading was proposed. Four-point bending seismic loading tests were performed using piping specimen in order to confirm the applicability of the proposed method to the piping. It was indicated that the crack growth behavior on piping could be evaluated conservatively using the proposed method, while the crack growth behavior due to seismic loading is evaluated non-conservatively by the existing method. (author)
Additional details
Publishing Information
- Journal Title
- Nippon Kikai Gakkai Ronbunshu, A Hen
- Journal Volume
- 79
- Journal Issue
- 802
- Journal Page Range
- p. 730-734
- ISSN
- 0387-5008
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 45080431
- Subject category
- S42: ENGINEERING;
- Descriptors DEI
- CARBON STEELS; COMPRESSION STRENGTH; FATIGUE; FINITE ELEMENT METHOD; INTEGRAL EQUATIONS; MECHANICAL TESTS; NUCLEAR POWER PLANTS; PIPES; RECOMMENDATIONS; SEISMIC EFFECTS; VALIDATION; WATER COOLED REACTORS
- Descriptors DEC
- ALLOYS; CALCULATION METHODS; CARBON ADDITIONS; EQUATIONS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS TESTING; MATHEMATICAL SOLUTIONS; MECHANICAL PROPERTIES; NUCLEAR FACILITIES; NUMERICAL SOLUTION; POWER PLANTS; REACTORS; STEELS; TESTING; THERMAL POWER PLANTS; TRANSITION ELEMENT ALLOYS; TUBES
Optional Information
- Notes
- 6 refs., 6 figs., 1 tab.