Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Coupling coarse mesh CFD with fine mesh CFD for modeling for Molten Salt Reactors in the Virtual Test Bed VTB

Conference ·
OSTI ID:2480350
The Nuclear Energy Advanced Modeling and Simulation (NEAMS) program aims at developing a simulation tool kit to accelerate the development and deployment of nuclear power technologies. NEAMS multiphysics tools have been designed to provide numerical simulation support for the design and licensing of GEN IV reactors. Pronghorn is NEAMS’s coarse-mesh computational fluid dynamics (CFD) tool, which is designed to run 3D core transients in GEN IV reactors at a reduced computational cost. To increase their accuracy, coarse-mesh CFD simulations require calibrated closure coefficients. One way of computing these coefficients is via the Nek5000, NEAMS’s high-fidelity CFD tool. This article discusses our current research lines in informing Pronghorn closure coefficients via Nek5000 to enable multiphysics simulations of the core cavity of the molten-salt fast reactor. We present an application in which Pronghorn mixing length turbulent viscosity has been calibrated from Nek5000 simulations. The resulting Pronghorn thermal-hydraulics model is then coupled to Griffin, the NEAMS neutron transport solver, to solve for the steady-state configuration of the molten-salt fast reactor.
Research Organization:
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Sponsoring Organization:
62
DOE Contract Number:
AC07-05ID14517;
OSTI ID:
2480350
Report Number(s):
INL/CON-21-65062-Rev000
Conference Information:
Physor 2022, Pittsburgh, 05/15/2022 - 05/20/2022
Country of Publication:
United States
Language:
English

Similar Records

Coupling coarse-mesh CFD with fine-mesh CFD for modeling molten-salt reactors in the Virtual Test Bed (VTB)
Conference · Fri Jul 01 00:00:00 EDT 2022 · OSTI ID:23203870

CFD simulations of Molten Salt Fast Reactor core cavity flows
Journal Article · Tue May 14 20:00:00 EDT 2024 · Nuclear Engineering and Design · OSTI ID:2447993