Multiphysics simulation of the molten salt fast reactor using Griffin and Pronghorn
Creators
- 1. Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415-3860 (United States)
- 2. Texas AM University, 400 Bizzell St, College Station, TX 77843 (United States)
Description
Molten-salt reactors (MSR) are tightly-coupled multiphysics systems: neutronics and thermal-hydraulics conditions strongly interact during steady-state and transient operations. Multiphysics Object-Oriented Simulation Environment (MOOSE) based tools are ideally suited for the simulations of coupled neutronic-thermal hydraulic transient simulation of MSRs. This paper presents the capability of two specific MOOSE-based applications, Griffin and Pronghorn, to simulate MSR designs. The incompressible flow equations in their Boussinesq approximation are then solved in Pronghorn, while Griffin models the neutronics using a multigroup diffusion model. The set of equations are discretized using the continuous finite element method (CFEM). The multigroup diffusion and the neutron precursors equations are solved as a monolithic system of equations using a Preconditioned Jacobian-Free Newton Krylov (PJFNK) method, while the Newton method is used to solve the pseudo transient incompressible flow equations. The two problems exchange power density and fluid temperature during the pseudo-transient and the simulation is run long enough to let the two physics converge to a steady state. A simplified MSR model has been set up to test the neutron precursors convection system in a realistic core configuration. The steady state analysis shows that the results are in accordance with the values found in the literature for this simplified design, but the design must be further refined to avoid localized undesired effects. A sensitivity analysis performed using the steady-state model shows that the reactor model behaves as expected, and provides valuable information on the importance of some of the design parameters
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. 2398-2412
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
- 54119380
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; CONVECTION; FAST REACTORS; FINITE ELEMENT METHOD; INCOMPRESSIBLE FLOW; MOLTEN SALT REACTORS; MOLTEN SALTS; NEUTRON TRANSPORT; NEUTRONS; NEWTON METHOD; POWER DENSITY; REACTOR DESIGN; SENSITIVITY ANALYSIS; STEADY-STATE CONDITIONS; THERMAL HYDRAULICS; TRANSIENTS
- Descriptors DEC
- BARYONS; CALCULATION METHODS; DESIGN; ELEMENTARY PARTICLES; ENERGY TRANSFER; EPITHERMAL REACTORS; FERMIONS; FLUID FLOW; FLUID MECHANICS; HADRONS; HEAT TRANSFER; HYDRAULICS; ITERATIVE METHODS; MASS TRANSFER; MATHEMATICAL SOLUTIONS; MECHANICS; NEUTRAL-PARTICLE TRANSPORT; NUCLEONS; NUMERICAL SOLUTION; RADIATION TRANSPORT; REACTOR LIFE CYCLE; REACTORS; SALTS; SIMULATION
Optional Information
- Notes
- 22 refs.; Virtual meeting