Multiphysics simulations for LWR analysis
Creators
- 1. Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 37831 (United States)
- 2. Department of Nuclear Engineering, Texas A and M University (United States)
- 3. Department of Chemical and Nuclear Engineering, University of New Mexico (United States)
Description
Accurate prediction of the neutron and temperature distributions within an operating nuclear reactor requires the solution of multiple coupled physics equations. In a light water reactor (LWR), there is a very strong coupling between the power distribution (described by the radiation transport equation) and the temperature and density distributions (described by a thermal diffusion equation in combination with a fluid flow model). This study aims to begin to quantify the impact of such feedback mechanisms as well as identify numerical difficulties associated with such multiphysics problems. A description of the multiphysics model and current solution strategy within the Exnihilo code package for coupling between 3-D radiation transport and 3-D heat transfer is given. Numerical results detailing the effects of varying the nature of the coupling and the impact of mesh refinement for a representative 3x3 pressurized water reactor (PWR) 'mini-assembly' are presented. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park (United States)
- ISBN
- 978-0-89448-700-2
- Imprint Title
- Proceedings of the 2013 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering - M and C 2013
- Imprint Pagination
- 3016 p.
- Journal Page Range
- p. 1797-1808
Conference
- Title
- 2013 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering
- Acronym
- M and C 2013
- Dates
- 5-9 May 2013
- Place
- Sun Valley, ID (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 45033794
- Subject category
- S97: MATHEMATICAL METHODS AND COMPUTING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Quality check status
- Yes
- Descriptors DEI
- EQUATIONS; FLUID FLOW; MATHEMATICAL SOLUTIONS; NEUTRONS; POWER DISTRIBUTION; PWR TYPE REACTORS; RADIANT HEAT TRANSFER; RADIATION TRANSPORT; SIMULATION; TEMPERATURE DISTRIBUTION; THERMAL DIFFUSION;
- Descriptors DEC
- BARYONS; DIFFUSION; ELEMENTARY PARTICLES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FERMIONS; HADRONS; HEAT TRANSFER; NUCLEONS; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS;
Optional Information
- Lead record
- cgjt4-fyf07
- Notes
- 14 refs.