Published May 1992
| Version v1
Miscellaneous
Careful determination of inservice inspection of piping by computer analysis in nuclear power plant
Creators
- 1. Korea Aatomic Energy Research Institute, Daejeon (Korea, Republic of)
Description
Stress analysis has been performed using computer program ANSYS in the pressurizer surge line in order to predict possibility of crack generation due to thermal stratification phenomena in pipes connected to reactor coolant system of Nuclear power plants. Highly vulnerable area to crack generation has been chosen by the analysis of fatigue due to thermal stress in pressurizer surge line. This kind of result can be helpful to choose the location requiring intensive care during inservice inspection of nuclear power plants.
Additional details
Publishing Information
- Publisher
- KSNT
- Imprint Place
- Seoul (Korea, Republic of)
- Imprint Title
- Proceedings of the Korean Society for Nondestructive Testing Spring Meeting 1992
- Imprint Pagination
- 77 p.
- Journal Page Range
- p. 36-43
Conference
- Title
- 1992 Spring Meeting of the Korean Society for Nondestructive Testing
- Dates
- 20 May 1992
- Place
- Seoul (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 45069694
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- A CODES; CRACKS; IN-SERVICE INSPECTION; NUCLEAR POWER PLANTS; PIPES; REACTOR COOLING SYSTEMS; STRESS ANALYSIS; SURGES
- Descriptors DEC
- COMPUTER CODES; COOLING SYSTEMS; ENERGY SYSTEMS; INSPECTION; NUCLEAR FACILITIES; POWER PLANTS; REACTOR COMPONENTS; THERMAL POWER PLANTS; TUBES
Optional Information
- Notes
- 7 figs, 2 tabs