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华龙一号核电厂中,在蒸汽发生器二次侧设置了非能动余热排出系统(PRS系统),可排出72 h内的堆芯剩余发热。为验证PRS系统能力,建立了三代核电非能动余热排出演示试验装置(ESPRIT)。该装置与华龙一号核电厂PRS系统高度比为1:1。开展了稳态运行和瞬态工况模拟试验,本文利用建立的RELAP5程序模型模拟了试验过程。与试验结果的比较显示RELAP5程序模拟两相自然循环现象的能力较好,但模拟蒸汽直接接触凝结的能力略有不足。
In the Hualong-1 nuclear power plant, a non-active residual heat removal system (PRS system) is installed on the secondary side of the steam generator to discharge the remaining core heat within 72 hours. In order to verify the capability of PRS system, a three-generation non-active residual heat removal demonstration device (ESPRIT) was established. The device and Hualong nuclear power plant PRS system height ratio of 1: 1. The steady-state operation and transient condition simulation tests are carried out. In this paper, the RELAP5 program model is established to simulate the test process. The comparison with the experimental results shows that the RELAP5 program has better ability to simulate natural circulation of two phases, but the ability of simulated steam to directly contact with coagulation is slightly insufficient.