Assessment of the Level of Natural Circulation of VVER-1000 Coolant on the Basis of Experimental Data from the Balakovo NPP

被引:0
|
作者
Kuznetsov, D. Yu. [1 ]
Aminov, R. Z. [2 ]
Yurin, V. E. [3 ]
机构
[1] Balakovo NPP, Balakovo, Russia
[2] Russian Acad Sci, Saratov Sci Ctr, Saratov, Russia
[3] Saratov State Tech Univ, Saratov, Russia
基金
俄罗斯科学基金会;
关键词
D O I
10.1007/s10512-023-00994-5
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
Given the obligation to safely navigate a full de-energization condition of NPP it is important to study the natural circulation of the coolant in the primary loop of NPP with water-moderated/cooled [pressurized-water] reactors in the event of de-energization of the main circulation pump. At Balakovo NPP No. 3 with 104% load, the power unit underwent complete de-energized along with the main circulation pumps. When switching to natural circulation of the coolant, the temperature in the hot legs dropped from 320 to 300 & DEG;C. This attests reliable and stable cooling of the core in the condition of natural circulation. A coefficient is proposed for assessing the level of natural circulation. It can be used to determine the flow rate of the circulating coolant on full de-energization of the main circulation pumps. Based on the measurements of the standard information- computational system of a power unit, the residual power release and the coefficient of natural circulation were determined in the entire area of work with the main circulation pumps de-energized for 45 min.
引用
收藏
页码:191 / 195
页数:5
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