Coupled neutronics and thermal-hydraulics numerical simulations of a Molten Salt Fast Reactor (MSFR) - IN2P3 - Institut national de physique nucléaire et de physique des particules Access content directly
Conference Papers Year : 2014

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.
No file

Dates and versions

in2p3-00904703 , version 1 (15-11-2013)

Identifiers

  • HAL Id : in2p3-00904703 , version 1

Cite

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⟩
21 View
0 Download

Share

Gmail Facebook X LinkedIn More