Published 1999
| Version v1
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A large break pipe accident of the AP600 reactor coolant system (RCS) pressure boundary
Creators
- 1. Center for Development of Nuclear Safety Technology, National Nuclear Energy Agency, Serpong (Indonesia)
Description
The large break pipe accident for AP600 has been analyzed. The analysis was done to evaluate the performance of protection system (Reactor Trip followed by Pump Trip) and mitigation system (CMT, ACC and IRWST) of the AP600 in order to limit the maximum fuel element cladding temperature so it does not exceed the acceptance criteria. Based on the accident sequences determined, the simulation was done by using PCTRAN Code. The analysis shows that the peak cladding temperature (PCT) which be reached is 698,8oC in case of cold leg break.This PCT is of course below the regulatory limit of 2200 of (1204oC) in the 10 CFR 50.46
Files
31042151.pdf
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(151.7 kB)
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Additional details
Additional titles
- Original title (Indonesian)
- Kecelakaan pipa pecah ukuran besar pada sistem primer reaktor daya AP600
Publishing Information
- Imprint Title
- Proceedings of the Fourth Scientific Presentation on Reactor Safety Technology
- Imprint Pagination
- 203 p.
- Journal Page Range
- p. 14-22
- ISSN
- 1410-0533
- Report number
- INIS-ID--004
Conference
- Title
- 4. Scientific Presentation on Reactor Safety Technology
- Original Conference Title
- Presentasi Ilmiah Teknologi Keselamatan Reaktor IV
- Dates
- 5 May 1999
- Place
- Serpong (Indonesia)
INIS
- Country of Publication
- Indonesia
- Country of Input or Organization
- Indonesia
- INIS RN
- 31042151
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCIDENTS; CLADDING; COMPUTER CODES; FUEL ELEMENTS; MITIGATION; POWER REACTORS; PWR TYPE REACTORS; REACTOR COOLING SYSTEMS; REACTOR PROTECTION SYSTEMS
- Descriptors DEC
- COOLING SYSTEMS; DEPOSITION; ENERGY SYSTEMS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SURFACE COATING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 5 refs.; 1 tab.; 4 figs. Imprint:Prosiding presentasi ilmiah teknologi keselamatan nuklir IV