Two-loop PWR RELAP5 to TRACE Model Conversion and Three Dimensional Vessel Model Development for Coolant Mixing Analysis - 14157
Creators
- 1. Jozef Stefan Institute, Jamova cesta 39, SI-1000 Ljubljana (Slovenia)
Description
The analysis of some Design Basis Accidents requires multidimensional prediction of the thermal-hydraulic conditions in order to realistically simulate the accident. The main goal of the paper is to present the ongoing development of a model suitable for analyzing the coolant mixing phenomena in the reactor pressure vessel (RPV) of a Westinghouse (W) two-loop pressurized water reactor (PWR). The model is being developed using the best-estimate system code Trac-Relap Advanced Computational Engine (TRACE) and consists of a one dimensional model of a W two-loop PWR with a three-dimensional model of the RPV. The one dimensional TRACE input deck was converted from an existing RELAP5 input model using the Symbolic Nuclear Analysis Package (SNAP) conversion plug-in following the Jozef Stefan Institute (JSI) RELAP5 to TRACE conversion method. The three-dimensional TRACE model has been obtained by replacing the one-dimensional model of the RPV in the developed TRACE one dimensional input model with a three-dimensional model of the RPV. The three-dimensional model of the RPV has been developed using the TRACE specialized VESSEL component. Besides the presentation of the development of TRACE one dimensional and three dimensional models a preliminary steady-state calculation using the new TRACE one dimensional model is presented. For calculations, the latest TRACE V5.0 Patch 3 computer code was used. Finally, the TRACE one dimensional calculation results are compared with the RELAP5 calculation results. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park, IL (United States)
- ISBN
- 978-0-89448-776-7
- Imprint Pagination
- 7 p.
Conference
- Title
- International Congress on Advances in Nuclear Power Plants
- Acronym
- ICAPP 2014
- Dates
- 6-9 Apr 2014
- Place
- Charlotte, NC (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 54022540
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CODES; CONVERSION; COOLANTS; DESIGN-BASIS ACCIDENTS; NUCLEAR INDUSTRY; ONE-DIMENSIONAL CALCULATIONS; PRESSURE VESSELS; PWR TYPE REACTORS; STEADY-STATE CONDITIONS; THERMAL HYDRAULICS; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- ACCIDENTS; CONTAINERS; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; INDUSTRY; MECHANICS; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 9 refs.; Available on CD-ROM from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)