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Investigation on Modeling Thermal-hydraulic System of CPR1000 NPP Based on RELAP5

机译:基于RELAP5的CPR1000核电厂热力液压系统建模研究。

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Based on the best-estimate program RELAP5/MOD4.0, a full-scope thermal-hydraulic model with reference to CPR1000 nuclear power plant is established in this paper, which includes the thermal-hydraulic systems of conventional island as well as the primary nuclear island which has already been researched in traditional safety analysis. Therefore, this paper mainly details the numerical model of the turbine and other parts of the conventional island thermodynamic system. A comparison between the calculated results in steady-state and the actual data of reactor demonstrates a fine consistency, thus verifying the accuracy and reliability of the model. In addition, the steam parameter changes are numerically simulated during the steam turbine's off-design operating condition such as back pressure variation and the variation trends are the same as the actual situation of nuclear power plants.
机译:基于最佳估计程序RELAP5 / MOD4.0,建立了参考CPR1000核电站的全范围热工水力模型,该模型包括常规岛的热工水力系统以及一次核电站的热工水力系统。传统安全分析中已经研究过的小岛。因此,本文主要详细介绍了常规岛式热力系统的涡轮机和其他部件的数值模型。稳态计算结果与反应堆实际数据之间的比较显示出良好的一致性,从而验证了模型的准确性和可靠性。另外,在汽轮机的非设计运行条件下,如背压变化,对蒸汽参数的变化进行了数值模拟,其变化趋势与核电站的实际情况相同。

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