Preliminary thermal-hydraulic core design of the Molten Salt Fast Reactor (MSFR)

被引:51
作者
Rouch, H. [1 ]
Geoffroy, O. [1 ]
Rubiolo, P. [2 ]
Laureau, A. [2 ]
Brovchenko, M. [2 ]
Heuer, D. [2 ]
Merle-Lucotte, E. [2 ]
机构
[1] INOPRO, F-38250 Villard De Lans, France
[2] Grenoble INP, UJF, LPSC IN2P3 CNRS, F-38026 Grenoble, France
关键词
MSFR; Molten salt reactor; Thermal-hydraulics design; Core cavity; CFD; Fuel salt temperature; MSBR;
D O I
10.1016/j.anucene.2013.09.012
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
A thermal-hydraulics study of the core of the Molten Salt Fast Reactor (MSFR) is presented. The numerical simulations were carried-out using a Computation Fluid Dynamic code. The main objectives of the thermal-hydraulics studies are to design the core cavity walls in order to increase the overall flow mixing and to reduce the temperature peaking factors in the salt and on the core walls. The results of the CFD simulations show that for the chosen core design acceptable temperature distributions can be obtained by using a curved core cavity shape, inlets and outlets. The hot spot temperature is less than 10 degrees C above the average core outlet temperature and is located in the centre of the top wall of the core. The results show also a moderate level of sensitivity to the working point. (C) 2013 Elsevier Ltd. All rights reserved.
引用
收藏
页码:449 / 456
页数:8
相关论文
共 15 条
[1]   DESIGN AND PERFORMANCE FEATURES OF A SINGLE-FLUID MOLTEN-SALT BREEDER REACTOR [J].
BETTIS, ES ;
ROBERTSON, RC .
NUCLEAR APPLICATIONS AND TECHNOLOGY, 1970, 8 (02) :190-+
[2]  
Bird R B., 2002, Transportphenomena
[3]  
Brovchenko M., 2012, P INT C PHYSOR 2012
[4]   Reactor physic and reprocessing scheme for innovative molten salt reactor system [J].
Delpech, S. ;
Merle-Lucotte, E. ;
Heuer, D. ;
Allibert, M. ;
Ghetta, V. ;
Le-Brun, C. ;
Doligez, X. ;
Picard, G. .
JOURNAL OF FLUORINE CHEMISTRY, 2009, 130 (01) :11-17
[5]  
Forsberg C.W., 2007, REV GEN NUCL, V4, P63
[6]  
GIF (Generation IV International Forum), 2008, ANN REP 2008
[7]   The thorium molten salt reactor:: Moving on from the MSBR [J].
Mathieu, L. ;
Heuer, D. ;
Brissot, R. ;
Garzenne, C. ;
Le Brun, C. ;
Lecarpentier, D. ;
Liatard, E. ;
Loiseaux, J. -M. ;
Meplan, O. ;
Merle-Lucotte, E. ;
Nuttin, A. ;
Walle, E. ;
Wilson, J. .
PROGRESS IN NUCLEAR ENERGY, 2006, 48 (07) :664-679
[8]   Possible Configurations for the Thorium Molten Salt Reactor and Advantages of the Fast Nonmoderated Version [J].
Mathieu, L. ;
Heuer, D. ;
Merle-Lucotte, E. ;
Brissot, R. ;
Le Brun, C. ;
Liatard, E. ;
Loiseaux, J. -M. ;
Meplan, O. ;
Nuttin, A. .
NUCLEAR SCIENCE AND ENGINEERING, 2009, 161 (01) :78-89
[9]   Introduction to the physics of molten salt reactors [J].
Merle-Lucotte, E. ;
Heuer, D. ;
Allibert, M. ;
Ghetta, V. ;
Le Brun, C. .
MATERIALS ISSUES FOR GENERATION IV SYSTEMS: STATUS, OPEN QUESTIONS AND CHALLENGES, 2008, :501-+
[10]  
Merle-Lucotte E., 2009, ADV NUCL FUEL MANAGE