Development of complex systems for automating nuclear power facilities

被引:0
作者
Lysikov, B. V. [1 ]
Kondratyev, V. V. [1 ]
Mikhailov, M. N. [1 ]
Potapova, V. P. [1 ]
Ukharov, S. G. [1 ]
机构
[1] Dollezhal Res & Dev Inst Power Engn NIKIET, Moscow, Russia
关键词
Power Unit; Research Reactor; Reactor Facility; Emergency Protection; Core Height;
D O I
10.1007/s10512-012-9588-4
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The basic advances made at the Dollezhal Research and Development Institute of Power Engineering in the development of the control systems and means for civilian nuclear power facilities are presented. Individual means (sensors, executing mechanisms and apparatus) and systems as a whole in the evolutionary development are reviewed in brief. The results of a comparative analysis of foreign and domestic regulatory documents, performed to substantiate the requirements for safety and control systems, are presented. The results of new developments and adoption of control systems for power units with RBMK, commercial and research reactors and new power reactor facilities in the design stage are presented. The level reached for the new systems is evaluated and the main recommendations for their further development are formulated.
引用
收藏
页码:11 / 16
页数:6
相关论文
共 3 条
[1]  
Lysikov B. V., 2005, VOPR AT NAUK TEKH OB, P5
[2]  
Mikhailov M. N., 2010, BEZOP OKR SREDY, P90
[3]  
[Михайлов М.Н. Mikhajlov M.N.], 2007, [Атомная энергия, Atomnaya energiya], V103, P55