PARCS-Subchanflow-Transuranus multiphysics coupling for improved PWR's simulations
- 1. Institute of Neutron Physics and Reactor Technology, Karlsruhe Institute of Technology, Eggenstein-Leopoldshafen (Germany)
- 2. Lehrstuhl für Nukleartechnik, Technische Universität München, Garching bei München (Germany)
Description
Increasing the prediction accuracy of the simulators' solvers is a constant effort in the nuclear academic and industry communities. In an evolutionary approach, the NRC's neutronics core simulator PARCS is being integrated with KIT's subchannel code Subchanflow (SCF) and JRC Karlsruhe's fuel behavior code Transuranus (TU) into a single code, PARCS-SCF-TU. A loose, nodal level coupling using the Operator-Splitting (OS) technique was implemented. So far, the 2-way steady state solution has been implemented and the transient coupling is under development. Having Transuranus in the coupling allows a better modeling and feedback of the fuel and clad temperature taking into account the local thermal hydraulics and burnup conditions. One of the objectives of this coupling is the future modeling of the RIA accident for high burnup conditions, where the fuel behavior properties and fuel temperature modeling are of relevant importance. In this paper, results obtained with PARCS-SCF, PARCS-SCF-TU and PARCS standalone for the PWR MOX/UO2 core transient benchmark as part of the testing and verification of the multiphysics codes under development will be presented and discussed. Also, preliminary PARCS-SCF-TU results showing the impact of modeling the fuel temperature with a fuel behavior code will be given. (author)
Additional details
Publishing Information
- Imprint Title
- Proceedings of 2017 international congress on advances in nuclear power plants (ICAPP2017)
- Imprint Pagination
- 2573 p.
- Journal Page Range
- 8 p.
Conference
- Title
- 2017 international congress on advances in nuclear power plants
- Acronym
- ICAPP2017
- Dates
- 24-25 Apr 2017; 26-28 Apr 2017
- Place
- Fukui (Japan); Kyoto (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 49024675
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BURNUP; COMPUTERIZED SIMULATION; FLOW MODELS; MIXED OXIDE FUELS; P CODES; POWER DISTRIBUTION; PWR TYPE REACTORS; REACTOR CORES; REACTOR SIMULATORS; TEMPERATURE DISTRIBUTION; THERMAL HYDRAULICS; THREE-DIMENSIONAL CALCULATIONS; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; ANALOG SYSTEMS; CHALCOGENIDES; COMPUTER CODES; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FLUID MECHANICS; FUELS; FUNCTIONAL MODELS; HYDRAULICS; MATERIALS; MATHEMATICAL MODELS; MECHANICS; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SIMULATION; SIMULATORS; SOLID FUELS; THERMAL REACTORS; URANIUM COMPOUNDS; URANIUM OXIDES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Available as CD-ROM Data in PDF format. Folder Name: pdf; Paper ID: 17096.pdf; 13 refs., 12 figs., 3 tabs.