Innovative development of nuclear power in Russia

被引:0
|
作者
V. G. Asmolov
A. V. Zrodnikov
M. I. Solonin
机构
[1] Rosénergoatom Concern,
[2] State Science Center of the Russian Federation — A. I. Leipunskii Physics and Power Engineering Institute,undefined
[3] Tvél Concern,undefined
来源
Atomic Energy | 2007年 / 103卷
关键词
Uranium; Plutonium; Nuclear Power Plant; Fast Reactor; Fuel Cycle;
D O I
暂无
中图分类号
学科分类号
摘要
The basic principles for performing analysis and the systems requirements for large-scale nuclear power in our country are formulated. The problems of modern nuclear power are examined and ways for modern nuclear power to transition to innovative development while satisfying these systems requirements for fuel use, handling spent fuel and wastes, and nonproliferation are indicated. The basic scenario of innovative development in the near term (up to 2030) is based on using predominantly 235U as fuel and water-moderated water-cooled reactors, which have been well mastered, for increasing nuclear capacities with limited introduction of fast reactors for solving the problem of spent fuel from thermal reactors. In the long term (2030–2050), a transition to 238U as the primary raw material with fast reactors predominating and complete closure of the nuclear power fuel cycle will be made.
引用
收藏
页码:665 / 674
页数:9
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