Coupled multiphysics multiscale transient simulations of the Mk1-FHR reactor using finite volume capabilities of the MOOSE framework
Creators
- 1. Computational Frameworks, Idaho National Laboratory, Idaho Falls, ID, 834015 (United States)
- 2. Thermal Fluids System Methods and Analysis, Idaho National Laboratory, Idaho Falls, ID 834015 (United States)
- 3. Reactor Physics Method and Analysis, Idaho National Laboratory, Idaho Falls, ID 834015 (United States)
- 4. Advanced Reactor Technology and Design, Idaho National Laboratory, Idaho Falls, ID 834015 (United States)
- 5. Argonne National Laboratory, 9700 S. Cass Avenue, IL 60439-4854 (United States)
Description
Multiphysics simulations are key to reactor safety analysis, especially for novel reactor designs lacking experimental data. Simulation tools within the multiphysics object-oriented simulation environment (MOOSE) framework, such as the Griffin reactor physics application and the coarse mesh computational fluid dynamics solver Pronghorn, can be coupled to perform such multiphysics transient simulations. We feature those capabilities in tightly-coupled multiphysics transient simulations of a simplified Mk1 pebble bed fluoride-salt-cooled high temperature (PB-FHR) reactor. A porous media model based on the incompressible Navier Stokes equation was implemented using the finite volume method for this work. This leverages the newly implemented finite volume discretization feature in MOOSE. (authors)
Availability note (English)
Available from the American Nuclear Society, 555 North Kensington Avenue, La Grange Park, Illinois 60526 (US)Additional details
Publishing Information
- Publisher
- ANS - American Nuclear Society
- Imprint Place
- La Grange Park (United States)
- Imprint Title
- Proceedings of the international conference on mathematics and computational methods applied to nuclear science and engineering - M and C 2021
- Imprint Pagination
- 2418 p.
- Journal Page Range
- p. 2267-2278
Conference
- Title
- International conference on mathematics and computational methods applied to nuclear science and engineering
- Acronym
- M and C 2021
- Dates
- 3-7 Oct 2021
- Place
- Raleigh, NC (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 54119367
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; FLUID MECHANICS; NAVIER-STOKES EQUATIONS; POROUS MATERIALS; REACTOR DESIGN; REACTOR PHYSICS; REACTOR SAFETY; SAFETY ANALYSIS
- Descriptors DEC
- DESIGN; DIFFERENTIAL EQUATIONS; EQUATIONS; MATERIALS; MECHANICS; PARTIAL DIFFERENTIAL EQUATIONS; PHYSICS; REACTOR LIFE CYCLE; SAFETY; SIMULATION
Optional Information
- Notes
- 24 refs.; Virtual meeting