New breeding gain definitions and their application to the optimization of a molten salt reactor design

被引:15
作者
Nagy, K. [1 ]
Kloosterman, J. L. [1 ]
Lathouwers, D. [1 ]
van der Hagen, T. H. J. J. [1 ]
机构
[1] Delft Univ Technol, Dept Radiat Radionuclides & Reactors, NL-2629 JB Delft, Netherlands
关键词
Molten salt reactor; Thorium fuel cycle; Breeding; CONVERTER REACTORS; FUEL;
D O I
10.1016/j.anucene.2010.09.024
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
The molten salt reactor (MSR) is an attractive breeder reactor. A graphite-moderated MSR can reach breeding because of the online salt processing and refueling. These features give difficulties when the breeding gain (BG) of the MSR is evaluated. The inventory of the core and external stockpiles have to be treated separately in order to quantify the breeding performance of the reactor. In this paper, an improved BG definition is given and it is compared with definitions used earlier. The improved definition was used in an optimization study of the graphite - salt lattice of the core. The aim of the optimization is a passively safe, self-breeder reactor. The fuel channel diameter, graphite volume and thorium concentration were varied while the temperature feedback coefficient of the core, BC - as defined in the paper and the lifetime of the graphite were calculated. There is a small range of lattices which provide both negative temperature feedback and breeding. Furthermore, breeding is possible only at low power densities in case of the salt processing efficiencies set in this study. In this range of power the lifetime of the graphite is between 12 and 20 years. (C) 2010 Elsevier Ltd. All rights reserved.
引用
收藏
页码:601 / 609
页数:9
相关论文
共 23 条
[1]   Thermodynamic properties and phase diagrams of fluoride salts for nuclear applications [J].
Benes, O. ;
Konings, R. J. M. .
JOURNAL OF FLUORINE CHEMISTRY, 2009, 130 (01) :22-29
[2]   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
[3]   FISSILE FUEL DYNAMICS OF BREEDER-CONVERTER REACTORS [J].
HARMS, AA .
ANNALS OF NUCLEAR ENERGY, 1978, 5 (02) :65-73
[4]  
Ignatiev V., 2007, P ICAPP 2007 INT C
[5]   THE MOLTEN-SALT REACTOR ADVENTURE [J].
MACPHERSON, HG .
NUCLEAR SCIENCE AND ENGINEERING, 1985, 90 (04) :374-380
[6]   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
[7]   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
[8]  
MATHIEU L, 2003, P GLOBAL 2003 INT C
[9]   Influence of the processing and salt composition on the thorium molten salt reactor [J].
Merle-Lucotte, Elsa ;
Mathieu, Ludovic ;
Heuer, Daniel ;
Ghetta, Veronique ;
Brissot, Roger ;
Le Brun, Christian ;
Liatard, Eric .
NUCLEAR TECHNOLOGY, 2008, 163 (03) :358-365
[10]  
MERLELUCOTTE E, 2008, P PHYSOR 2008 INT C