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.
引用
收藏
页码:6 / 13
页数:7
相关论文
共 50 条