Differences in LBLOCA thermal hydraulic response between 1D and 3D calculations
Creators
- 1. Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)
Description
Best Estimate (BE) calculation of large break Loss of Coolant Accident (LBLOCA) has been applied to the most of the domestic Nuclear Power Plants (NPP). One of the recent concerns in LBLOCA analysis of APR1400 design was a potential of the 'blowdown quenching', which drastically decreased the fuel cladding temperatures by the downflow of the water from the Upper Guide Structure (USG) of the reactor vessel to the core. Depending on its extent, the cladding temperature response during reflood phase can change greatly, and then the uncertainty of reflood phenomena such as downcomer boiling may be more important. Due to the concern, a more specific analysis such as three dimensional (3D) calculation, has been required for the LBLOCA thermal hydraulic response. The present study is to discuss the 3D calculation and its result in comparison with that from 1D calculation. Several differences and their reasons are also discussed. MARS KS code was used for the 1D and 3D calculation, and the hot channel whose flow area is not greater than area of one fuel assembly was used
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS autumn meeting
- Imprint Pagination
- [1 CD-ROM]
- Journal Page Range
- [2 p.]
Conference
- Title
- 2012 autumn meeting of the KNS
- Dates
- 24-26 Oct 2012
- Place
- Kyoungju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 44062733
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CLADDING; COMPUTER CALCULATIONS; DESIGN; FUEL ASSEMBLIES; LOSS OF COOLANT; PWR TYPE REACTORS; REACTOR CORES; REACTOR VESSELS; THERMAL HYDRAULICS
- Descriptors DEC
- ACCIDENTS; CONTAINERS; DEPOSITION; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; MECHANICS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SURFACE COATING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 2 refs, 5 figs