Published 2004
| Version v1
Miscellaneous
Stress corrosion crack growth evaluation in primary loop of nuclear power plant
- 1. Korea Electric Power Research Institute, Taejon (Korea, Republic of)
- 2. KOPEC, Yongin (Korea, Republic of)
- 3. Korea Hydro and Nuclear Power Co., Ltd., Seoul (Korea, Republic of)
Description
The most important mode of subcritical crack growth is primary water stress corrosion crack, which was the reported mechanism from the root cause analysis of the crack in the bimetallic welds. Stress corrosion crack growth evaluations was carried out for several flaw shapes of both axial and circumferential flaws, using the steady-state stresses including residual stresses. This evaluation considered the possibility of additional flaws in the primary loops of nuclear power plant, even though no such flaws have been identified by ultrasonic test. Consequently, results show that the predicted flaw sizes will determine acceptability for continued service and maintenance
Additional details
Publishing Information
- Publisher
- KSME
- Imprint Place
- Seoul (Korea, Republic of)
- Imprint Title
- Proceedings of the KSME 2004 spring annual meeting
- Imprint Pagination
- [CD-ROM]
- Journal Page Range
- [4 p.]
Conference
- Title
- 2004 spring annual meeting of the KSME
- Dates
- 28-30 Apr 2004
- Place
- Pyeongchang (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 35090002
- Subject category
- S36: MATERIALS SCIENCE; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CRACKING; DEFECTS; IN-SERVICE INSPECTION; MAINTENANCE; NUCLEAR POWER PLANTS; PRIMARY COOLANT CIRCUITS; RESIDUAL STRESSES; STRESS CORROSION; ULTRASONIC TESTING; WELDING
- Descriptors DEC
- ACOUSTIC TESTING; CHEMICAL REACTIONS; COOLING SYSTEMS; CORROSION; DECOMPOSITION; ENERGY SYSTEMS; FABRICATION; INSPECTION; JOINING; MATERIALS TESTING; NONDESTRUCTIVE TESTING; NUCLEAR FACILITIES; POWER PLANTS; PYROLYSIS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; STRESSES; TESTING; THERMAL POWER PLANTS; THERMOCHEMICAL PROCESSES
Optional Information
- Notes
- 6 refs, 4 figs, 1 tab