Possibilities of gas-Cooled Water-Moderated Reactors

被引：0
|
作者：
V. M. Kotov
G. A. Vityuk
A. S. Suraev
机构：
[1] Institute of Atomic Energy,
[2] National Nuclear Center of the Republic of Kazakhstan,undefined
来源：
Atomic Energy | 2014年 / 116卷
关键词：
Steam; Fuel Element; Fuel Assembly; Uranium Dioxide; Heat Shield;
D O I：
暂无
中图分类号：
学科分类号：
摘要：
This work is devoted to finding solutions to technical problems so as to improve the technical and economic performance of NPPs. The possibilities of using neutron moderation energy in gas-cooled water-moderated channel reactors and triple steam superheating in a Rankine cycle are examined. It is shown that a high degree of conversion into mechanical energy is attained, well-developed and widely used rod-shaped fuel elements can be used, and the fuel-element design is simple. The characteristics of the proposed reactor show its advantages over the HTGR and supercritical-water-cooled reactors.
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页码：6 / 13
页数：7
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