Breeding of 233U in the Thorium-Uranium Fuel Cycle in VVER Reactors Using Heavy Water

被引:2
|
作者
Marshalkin, V. E. [1 ]
Povyshev, V. M. [1 ]
机构
[1] Russian Fed Nucl Ctr, All Russian Res Inst Expt Phys VNIIEF, Pr Mira 37, Sarov 607188, Nizhny Novgorod, Russia
关键词
reactors kinetics; light water reactors; heavy water reactors; reactors with mixture of light and heavy water; oxide nuclear fuel; fuel breeding;
D O I
10.1134/S1063778815110113
中图分类号
O57 [原子核物理学、高能物理学];
学科分类号
070202 ;
摘要
A method is proposed for achieving optimal neutron kinetics and efficient isotope transmutation in the U-233-Th-232 oxide fuel of water-moderated reactors with variable water composition (D2O, H2O) that ensures breeding of the U-233 and U-235 isotopes. The method is comparatively simple to implement.
引用
收藏
页码:1274 / 1286
页数:13
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