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压水堆核电厂反应堆冷却剂系统自然循环能力是这种类型核电厂固有的安全性之一。本文介绍用轻水堆瞬态分析程序RE-TRAN-02,并根据秦山核电厂自然循环试验的步骤和测量的电厂参数来模拟分析计算不同反应堆功率下电厂自然循环冷却的能力;最后将试验后的分析结果与试验结果和试验前的分析作比较,以评价试验结果的可靠性以及分析中所采用的设备参数对分析计算的影响。
The natural circulation capability of PWR nuclear power plant reactor coolant systems is one of the inherent safety features of this type of NPP. In this paper, we use RE-TRAN-02, a transient analysis program of light-water reactor, and simulate and calculate the cooling capacity of natural circulation in power plant with different reactor power according to the steps of natural circulation test of Qinshan NPP and the measured plant parameters. Finally, The analysis results are compared with the test results and the pre-test analysis to evaluate the reliability of the test results and the influence of the equipment parameters used in the analysis on the analysis and calculation.