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.
机构:
Lab Phys Subatom & Cosmol, F-38026 Grenoble, France
Inst Max Von Laue Paul Langevin, F-38000 Grenoble, FranceLab Phys Subatom & Cosmol, F-38026 Grenoble, France
机构:
Lab Phys Subatom & Cosmol, F-38026 Grenoble, France
Inst Max Von Laue Paul Langevin, F-38000 Grenoble, FranceLab Phys Subatom & Cosmol, F-38026 Grenoble, France