Published 2004
| Version v1
Miscellaneous
A study on the applications of leak-before-break to RCS loop for Kori Unit 1 NPP
Creators
- 1. Korea Electric Power Research Institute, Taejon (Korea, Republic of)
Description
The development and application of the leak-Before-Break concept to Kori unit 1 nuclear power plant piping are reviewed. A general procedure and criteria of LBB are also introduced. In order to study feasibility of LBB, a limit load method and a J-T method are evaluated for comparison. Both methodologies are applied to the stainless steel and carbon steel of reactor coolant system. The stability of postulated through wall crack on the nuclear piping are verified with elastic-plastic fracture mechanics using finite element method. It is concluded that the limit load and J-T method are acceptable for nuclear piping materials
Additional details
Publishing Information
- Publisher
- KAIF
- Imprint Place
- Seoul (Korea, Republic of)
- Imprint Title
- Proceedings of the 19th KAIF/KNS annual conference
- Imprint Pagination
- 725 p.
- Journal Page Range
- p. 147-156
Conference
- Title
- 19. KAIF/KNS annual conference
- Dates
- 25-27 Apr 2004
- Place
- Seoul (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 36036190
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BREAKDOWN; FINITE ELEMENT METHOD; FRACTURE MECHANICS; KORI-1 REACTOR; LEAKS; PIPES; REACTOR COOLING SYSTEMS
- Descriptors DEC
- CALCULATION METHODS; COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; MATHEMATICAL SOLUTIONS; MECHANICS; NUMERICAL SOLUTION; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; TUBES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 7 refs, 9 figs, 3 tabs