Skip to Main content Skip to Navigation
Conference papers

Coupled neutronics and thermal-hydraulics numerical simulations of a Molten Salt Fast Reactor (MSFR)

Abstract : Coupled neutronics and thermalhydraulic numerical analyses of a molten salt fast reactor are presented. These preliminary numerical simulations are carried-out using the Monte Carlo code MCNP and the Computation Fluid Dynamic code OpenFOAM. The main objectives of this analysis performed at steady-reactor conditions are to confirm the acceptability of the current neutronic and thermalhydraulic designs of the reactor, to study the effects of the reactor operating conditions on some of the key MSFR design parameters such as the temperature peaking factor. The effects of the precursor’s motion on the reactor safety parameters such as the effective fraction of delayed neutrons have been evaluated.
Document type :
Conference papers
Complete list of metadatas

http://hal.in2p3.fr/in2p3-00904703
Contributor : Emmanuelle Vernay <>
Submitted on : Friday, November 15, 2013 - 9:53:47 AM
Last modification on : Monday, July 20, 2020 - 9:18:12 AM

Identifiers

  • HAL Id : in2p3-00904703, version 1

Collections

IN2P3 | LPSC | CNRS | UGA | GEPI

Citation

A. Laureau, P.R. Rubiolo, D. Heuer, E. Merle-Lucotte, M. Brovchenko. Coupled neutronics and thermal-hydraulics numerical simulations of a Molten Salt Fast Reactor (MSFR). Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo (SNA & MC 2013), Oct 2013, Paris, France. pp.02307. ⟨in2p3-00904703⟩

Share

Metrics

Record views

130