Incorporation of the procedure for monitoring coolant boiling in a VVER-1000 core into the in-reactor noise diagnostics system

被引:0
|
作者
Yu. M. Semchenkov
V. A. Mil’to
B. E. Shumskii
机构
[1] Russian Science Center Kurchatov Institute,
[2] Moscow Engineering-Physics Institute,undefined
来源
Atomic Energy | 2008年 / 105卷
关键词
Neutron Flux; Fuel Assembly; Noise Signal; Fuel Element Cladding; Coolant Parameter;
D O I
暂无
中图分类号
学科分类号
摘要
A method for performing diagnostics of coolant boiling in a VVER-1000 core is described. This method was developed at the Russian Science Center Kurchatov Institute and is based on monitoring the increase of the sensitivity of neutron flux noise to the fluctuations of the coolant parameters. This procedure is intended to be used as part of the in-reactor noise diagnostics system. It is now in commercial operation of the No. 3 unit of the Kalinin and two units of the Tianwan (China) nuclear power plants.
引用
收藏
页码:99 / 103
页数:4
相关论文
共 50 条