Published June 1998
| Version v1
Journal article
Safety analysis on fatigue cracking of pressurizer nozzle in nuclear power plant
- 1. Korea Electric Power Corp., Seoul (Korea, Republic of)
- 2. Korea Electric Power Research Institute, Taejon (Korea, Republic of)
Description
Based on the design transient, stress analysis and integrity evaluation, such as crack tolerance and fatigue crack growth, were performed on the cast head type pressurizer safety/relief nozzle corner. Large crack tolerance exists and fatigue crack growth of a postulated initial crack has been calculated to be very small. Therefore, the failure risk of nozzle corner was found to be low and the stopping ISI on the nozzle corner would be recommended. (author)
Additional details
Publishing Information
- Journal Title
- Transactions of the Korean Society of Mechanical Engineers. A
- Journal Volume
- 22
- Journal Issue
- 6
- Journal Page Range
- p. 1125-1133
- ISSN
- 1226-4873
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 29038577
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CRACK PROPAGATION; FATIGUE; IN-SERVICE INSPECTION; NOZZLES; NUCLEAR POWER PLANTS; PRESSURIZERS; SAFETY ANALYSIS; STRESS ANALYSIS
- Descriptors DEC
- INSPECTION; MECHANICAL PROPERTIES; NUCLEAR FACILITIES; POWER PLANTS; THERMAL POWER PLANTS