NUCLEAR AND BURN-UP CHARACTERISTICS OF SMALL MOLTEN-SALT POWER-REACTOR

被引:5
作者
MITACHI, K
FURUKAWA, K
MINAMI, K
KATO, Y
机构
[1] Dept. of Energy Eng., Toyohashi Univ. of Technol.
[2] Inst. of Res. & Development, Tokai Univ.
[3] Dept. of Sci. System Development, Fujitsu Ltd.
[4] Dept. of Fuels & Mater. Res., Japan At. Energy Res. Inst.
来源
JOURNAL OF THE ATOMIC ENERGY SOCIETY OF JAPAN | 1990年 / 32卷 / 04期
关键词
bum-up; chemical compositions; configuration; criticality; molten salt fueled reactors; molten salts; neutronic calculation; nuclear characteristics; reactor core; thorium; uranium; 233;
D O I
10.3327/jaesj.32.377
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 preliminary design study is performed for small molten-salt power reactors fueled with 233U. Nuclear characteristics of the reactor are analyzed by using two-dimensional diffusion and burn-up calculation code “CITATION” together with 9 group reactor constants. Two semioptimized reactors (initial cores) are found out after performing the design studies of 57 reactorcores which are different from each other in the fuel salt composition, the graphite volume ratio, the geometry and size etc. Bum-up characteristics are examined on the semi-optimized reactors for 1.000 days after beginning the reactor operation. It is found that the fuel conversion ratios of the reactors range of 0.98~1.00 without any continuous chemical processing except the fission gas removal. The reactor can be operated for about 25 years without any exchange of the core graphite, owing to the low neutron flux density. These results support that the small molten-salt power reactor has several advantages in the aspects of operation and maintenance, safety, nuclear proliferation resistance, energy resource problems etc. © 1990, Atomic Energy Society of Japan. All rights reserved.
引用
收藏
页码:377 / 384
页数:8
相关论文
共 7 条
[1]  
ROBERTSON R.C., Conceptual design study of a single-fluid molten-salt breeder reactor, ORNL-4541, (1970)
[2]  
Ebasco: 1,000 MWe MSBR conceptual design study, Final report-task I, TID-26156, (1972)
[3]  
ENGEL J.R., GRIMES W.R., BAUMAN H.F., Mc COY E.H., DEARING J.F., RHOADES W.A., Conceptual design characteristics of a denatured molten-salt reactor with once-through fueling, ONRL/TM-7207, (1980)
[4]  
FURUKAWA K., MINAMI K., OOSAWA T., OHTA M., NAKAMURA N., MITACHI K., KATO Y., Emerging Nuclear Energy Systems, (1987)
[5]  
FURUKAWA K., MINAMI K., MITACHI K., KATO Y., Compact molten-salt fission power stations and their developmental program, Proc. Int. Symp. Molten Salt, 87, 7, (1987)
[6]  
FURUKAWA K., MITACHI K., MINAMI K., KATO Y., High safety and economical small molten-salt fission power stations and their developmental program, Alternative Energy Sources VII, 2, (1989)
[7]  
MAYS G.T., SMITH A.N., ENGEL J.R., Distribution and behavior of tritium in the coolant-salt technology facility, ORNL/TM-5759, (1977)