首页> 外文会议>International conference on nuclear engineering >COUNTERMEASURES TO IMPROVE LWR SAFETY LEVEL IN DESIGN AND OPERATION BY ACCIDENT ANALYSES AT FUKUSHIMA DAIICHI NUCLEAR POWER PLANTS
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COUNTERMEASURES TO IMPROVE LWR SAFETY LEVEL IN DESIGN AND OPERATION BY ACCIDENT ANALYSES AT FUKUSHIMA DAIICHI NUCLEAR POWER PLANTS

机译:通过对福岛大地核电站的事故分析来提高轻水堆安全设计和运行水平的对策

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The 2011 off the Pacific coast of Tohoku Earthquake occurred on March 11. The earthquake attacked the Fukushima Daiichi nuclear power station with six boiling water reactors (BWRs), three out of which, units 1 through 3 in rated operation except for three reactors of units 4 through 6 in scheduled periodic inspection, automatically shut down in response to the intense seismic motion. Emergency diesel generators started to pump water to cool reactors, and an hour later, the back-up generators lost their all functions by the station blackout resulting from tsunami flooding. In this situation at the unit 1, the isolation condenser system (IC) should have made a critical role to keep the reactor pressure and water level to be safety by removing the decay heat by natural circulation. In fact at the unit 1 during the accident, IC valves were closed by fail-safe and could not have shown the ability of the designed function. An accident report gave general descriptions of the causes and results of accidents, but not the quantitative data indicative of details; therefore, it seems difficult to identify the specific problems in plant operations. Even in this case, if an appropriate analysis code is available for reproducing events based on the reports, it will be possible to determine individual data quantitatively and identify problems in plant operations. In our work, we used the nuclear reactor thermal-hydraulic code RETRAN-3D/MOD4, which has been approved and licensed by U.S. Nuclear Regulatory Commission, to model light water reactors (LWRs) and reproduce the circumstances of the 2011 Fukushima Daiichi nuclear accident as the simulation code. Here, we subjected transition analyses of the process on the core-meltdown accident, and put forward the system to prevent the accident, where the accident analysis report was employed to simulate conditions of the accident. It could enable us to suggest adequate operation procedures suitable for LWR to avoid the severe accident, and to propose countermeasures to improve LWR safety level in design and operation.
机译:2011年东北太平洋地震发生在3月11日。地震袭击了福岛第一核电站,该电站有6个沸水反应堆(BWR),其中3个为额定运行状态的1至3号机组,只有3个机组为反应堆4至6在预定的定期检查中,响应强烈的地震运动而自动关闭。紧急柴油发电机开始向冷却反应堆中抽水,一个小时后,由于海啸泛滥导致电站停电,备用发电机失去了所有功能。在1号机组的这种情况下,隔离冷凝器系统(IC)应该发挥关键作用,通过自然循环消除衰变热,从而保持反应堆压力和水位安全。实际上,在事故期间的1号机组上,IC阀已通过故障安全关闭,无法显示设计功能的能力。事故报告仅对事故的原因和结果进行了一般性描述,但没有提供表明细节的定量数据。因此,似乎很难确定工厂运营中的具体问题。即使在这种情况下,如果有适当的分析代码可用于根据报告重现事件,则有可能定量确定单个数据并确定工厂运营中的问题。在我们的工作中,我们使用了已获得美国核监管委员会批准并许可的核反应堆热工代码RETRAN-3D / MOD4,对轻水反应堆(LWR)进行建模,并重现了2011年福岛第一核电站事故的情况。作为模拟代码。在此,我们对核心熔毁事故进行了过程的过渡分析,并提出了预防事故的系统,其中使用事故分析报告来模拟事故的状况。它可以使我们提出适合轻水堆的适当操作规程,避免发生严重事故,并提出对策,以提高轻水堆在设计和运行中的安全水平。

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