论文部分内容阅读
秦山核电厂调试后失水事故计算分析中采用了高压安注系统和安注箱试验的测量结 果,重新分析了大、小破口失水事故。为使分析计算与FSAR有一个可比性,模拟计算采用的初始条件、计算模型及分析程序都与FSAR相同。计算分析的结果进一步确认了秦山核电厂大、小破口失水事故后的安全性,并为FSAR中大、小破口失水事故分析提供了修改的依据。另外,依据秦山核电厂ECCS设计特点和运行方式,并参照LWR失水事故安全准则,评述了秦山核电厂ECCS的设计能力、可靠性和冗余度。
Qinshan Nuclear Power Plant commissioning after the accident analysis and calculation of high-pressure steam injection system using the safety test results, re-analysis of large and small break water-loss accident. In order to make the analysis and calculation of a comparable FSAR, the initial conditions used in the simulation calculation, calculation model and analysis procedures are the same with FSAR. The results of the calculation and analysis further confirm the safety of Qinshan NPP after the water loss accident of large and small breaches, and provide the basis for the modification of the accident analysis of large and small breaches of the FSAR. In addition, according to the ECCS design features and operation mode of Qinshan NPP, and with reference to the LWR water loss accident safety criteria, the design capability, reliability and redundancy of Qinshan Nuclear Power Plant ECCS are reviewed.