Preliminary Evaluation of the Effect of Several Management Measures for the Station Blackout Severe Accident of the Pressurized Water Reactor Nuclear Power Plant
The recent Fukushima accident shows that for nuclear power plants, station blackout (SBO) is an important cause of core damage severe accident and radiological releases. In this paper, the typical three-loop pressurized water reactor (PWR) in China is modeled using an integrated severe accident analysis code, and the progression of the SBO accident sequence is also simulated. Then based on the analysis of the calculation results, several measures are adopted to mitigate the SBO accident. In spite of some negative effects, the analysis results show that the consequences of SBO severe accident can be effectively mitigated by restoration of the AC power supply, rapid depressurization of the primary system by opening the three safety valves, and feeding water into the steam generators.
Integrated analysis code Management measures Severe accident Station blackout
LUWen-kui ZHAO Bo
Technical Integration Division, China Nuclear Power Engineering Co. Ltd, P.R.China, 100840
国际会议
哈尔滨
英文
455-460
2011-11-24（万方平台首次上网日期，不代表论文的发表时间）