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EXPERIMENTAL STUDY ON THE STEAM LINE BREAK (SLB) ACCIDENT WITH THE STEAM GENERATOR TUBE RUPTURE (SGTR)

机译:蒸汽发生器爆破(SGTR)的蒸汽管道破裂(SLB)事故的实验研究

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The integral effect test to simulate a steam line break (SLB) accident accompanied by a steam generator tube rupture (SGTR), named SLB-SGTR-02 test, was performed to investigate the thermal hydraulic phenomena during a multiple failure accident. In this study, a thermal-hydraulic integral effect facility, ATLAS (Advanced Thermal-hydraulic test Loop for Accident Simulation) was utilized to simulate thermal hydraulic phenomena which can occur in the nuclear power plant, especially for the pressurized water reactor, as realistically as possible. The SLB is simulated as a guillotine break on the main steam line and, in the SGTR, five steam generator tubes on the steam generator hot-side are modeled. Due to the initiation of SLB, a reactor was tripped by low steam generator pressure (LSGP) signal and the SGTR was initiated when the water inventory in the secondary system of the affected steam generator was dried-out. During the transient simulation for SLB-SGTR-02 test, major thermal-hydraulic parameters such as the system pressures, the collapsed water levels, the flows in the primary loops and the fluid temperatures, were measured and analyzed. Through this experimental result, insights about the accident management procedure can be provided in the case of the multiple failure accident, such as an SLB with a SGTR.
机译:进行了模拟蒸汽管线破裂(SLB)事故并伴有蒸汽发生器管破裂(SGTR)的积分效应测试,称为SLB-SGTR-02测试,以研究多次失效事故期间的热力水力现象。在这项研究中,利用热液积分效应设施ATLAS(事故模拟的高级热液试验回路)来模拟可能在核电站中发生的热液现象,特别是对于压水反应堆。可能的。 SLB被模拟为主蒸汽管线上的断头台断裂,并且在SGTR中,对蒸汽发生器热侧的五个蒸汽发生器管进行了建模。由于SLB的启动,反应堆因蒸汽发生器压力低(LSGP)信号而跳闸,并且当受影响的蒸汽发生器的二次系统中的水存量变干时,SGTR被启动。在SLB-SGTR-02测试的瞬态模拟过程中,测量并分析了主要的热工液压参数,例如系统压力,塌陷的水位,主回路中的流量和流体温度。通过该实验结果,可以在发生多重故障事故(例如带有SGTR的SLB)的情况下提供有关事故管理程序的见解。

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