An experimental study on the fracture behavior of nuclear piping system with a circumferential crack (1) - estimation of crack behavior in straight piping -
- 1. Korea Institute of Nuclear Safety, Taejon (Korea, Republic of)
- 2. Engineering Mechanics Cooperation of Columbus, Columbus (United States)
Description
The purpose of this study is to investigate experimentally the effects of both seismic loading and crack length on the fracture behavior of piping system with a circumferential crack in nuclear power plants. The experiments were performed using both large scale piping system facility and 4 points bending test machine under PWR operating conditions. The difference in the load carrying capacities between cracked piping and non-cracked piping was also investigated using the results from experiments and numerical calculations. The results obtained from the experiments and estimation are as follows : (1) The safety margin under seismic loading is larger than those under quasi static loading or simple cyclic loading. (2) There was no significant effect of crack length on fracture behavior of piping system with both a surface crack and a through-wall crack. (3) The load carrying capacity in cracked piping was reduced by factors of 7 to 46 compared to non-cracked piping
Additional details
Publishing Information
- Journal Title
- Transactions of the Korean Society of Mechanical Engineers. A
- Journal Volume
- 23
- Journal Issue
- 7
- Series
- 24 refs., 12 figs., 5 tabs
- Journal Page Range
- p. 1182-1195
- ISSN
- 1226-4873
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 31059759
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S42: ENGINEERING;
- Descriptors DEI
- CRACKS; FRACTURES; LEAKS; LOADING; NUCLEAR POWER PLANTS; NUMERICAL ANALYSIS; PIPES; PWR TYPE REACTORS; SEISMIC EFFECTS
- Descriptors DEC
- ENRICHED URANIUM REACTORS; FAILURES; MATERIALS HANDLING; MATHEMATICS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; TUBES; WATER COOLED REACTORS; WATER MODERATED REACTORS