Prospects for development of nuclear power stations equipped with VVER reactors

被引:1
|
作者
Semchenkov Yu.M. [1 ]
Sidorenko V.A. [1 ]
机构
[1] Russian Scientific Center, Kurchatov Institute of Atomic Energy, Moscow 123182
关键词
Fuel Cycle; Reactor Core; Supercritical Pressure; Nuclear Power Engineering; VVER Reactor;
D O I
10.1134/S0040601511050119
中图分类号
学科分类号
摘要
The prospects for further development in Russia of nuclear stations equipped with water-cooled water-moderated reactors are considered. © 2011 Pleiades Publishing, Ltd.
引用
收藏
页码:361 / 369
页数:8
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