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

被引：5

作者：

Laureau, A. ^{[1
]}

Rubiolo, P. R. ^{[1
]}

Heuer, D. ^{[1
]}

Merle-Lucotte, E. ^{[1
]}

Brovchenko, M. ^{[1
]}

机构：

[1] Grenoble INP, CNRS, IN2P3, UJF,LPSC, 53 Rue Martyrs, F-38026 Grenoble, France

来源：

SNA + MC 2013 - JOINT INTERNATIONAL CONFERENCE ON SUPERCOMPUTING IN NUCLEAR APPLICATIONS + MONTE CARLO | 2014年

关键词：

coupled neutronics and thermalhydraulic analysis; CFD; Monte Carlo; Molten Salt Fast Reactor;

D O I：

10.1051/snamc/201402307

中图分类号：

TP39 [计算机的应用];

学科分类号：

081203 ; 0835 ;

摘要：

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.

引用

页数：10

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