Published October 2012 | Version v1
Miscellaneous

Differences in LBLOCA thermal hydraulic response between 1D and 3D calculations

  • 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

Part of:
Proceedings of the KNS autumn meeting

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