Fast reactor operating on uranium-plutonium oxide fuel in a self-regulatable regime

被引:3
作者
Gol'din, VY [1 ]
Pestryakova, GA [1 ]
Troshchiev, YV [1 ]
Aristova, EN [1 ]
机构
[1] Russian Acad Sci, Inst Math Stimulant, Moscow 117901, Russia
关键词
Oxide; Carbide; Uranium; Plutonium; Fast Reactor;
D O I
10.1023/A:1024242017112
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
Mathematical simulation is used to show that it is possible to develop a fast reactor operating on uranium plutonium oxide fuel (UO2)(1-x) (PuO2)(x), the same for all fuel elements in the core, and with uranium carbide in breeding elements with heavy coolant (PbBi eutectic). A self-regulatable regime is obtained in the reactor. This enhances safety while minimizing control. Tailings uranium with 0.1% U-235 and a mixture of plutonium isotopes, which is obtained from spent fuel, making it possible to conduct operation in an actinide-closed fuel cycle, is used in the fuel and uranium carbide. U-238 is actually consumed in the reactor, but most fission products are produced from Pu-239.
引用
收藏
页码:142 / 148
页数:7
相关论文
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