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Effect of External Water Injection on Core Degradation and Fission Product Release in Fukushima Unit 1 Accident

机译:外注水对福岛1号机组事故中岩心降解和裂变产物释放的影响

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The severe accident of Fukushima Daiichi occurred on March 11, 2011, which originated from an earthquake and tsunami. There were six units in the Fukushima Daiichi nuclear power station. Units 1, 2 and 3 were operating and Units 4, 5 and 6 were shutdown at that time. It was estimated that partial or full core degradation occurred in all three operating units, according to the results of Phase Ⅰ of OECD/NEA BSAF Project. Furthermore, it was estimated that a RPV lower head penetration failure might occur in the case of Units 1 and 3. Understanding the situation of the accident and tracking of the current molten corium locations are essential to conduct decontaminations and to control the site situations hereafter. Cooling of the reactor vessel and corium debris is one of the most important works to prevent or mitigate a severe accident. In the case of Units 1 and 2, it was well known that external water injection started after about 15 hours and 80 hours from the reactor scram, respectively. The amount of water reaching the reactor pressure vessel and the start time of the external water injection are crucial factors to remove the decay heat in the vessel and are directly related with the degree of core degradation. In this research, some relationships were observed between the core damage progression and the injection mass flow rate of water or the timing of the injection. Moreover, the actual injection water flow rate and the extent of fission products release were estimated by comparing the measured data (for instance, pressures of reactor vessel and drywell). MELCOR 2.1 was used in this study.
机译:福岛第一核电站的严重事故发生在2011年3月11日,起因于地震和海啸。福岛第一核电站有6个机组。当时1号,2号和3号机组正在运行,而4号,5号和6号机组已关闭。根据OECD / NEA BSAF项目第一阶段的结果,估计在所有三个运营单元中都发生了部分或全部堆芯退化。此外,据估计,在1号和3号机组的情况下,可能发生RPV较低的压头穿透故障。了解事故情况并跟踪当前熔融的皮质位置对于进行净化和控制今后的现场情况至关重要。反应堆容器和皮质碎片的冷却是防止或减轻严重事故的最重要的工作之一。在单元1和2的情况下,众所周知,分别在从反应堆炉渣开始大约15小时和80小时后开始外部注水。到达反应堆压力容器的水量和外部注水的开始时间是消除容器中衰减热的关键因素,并且与堆芯退化的程度直接相关。在这项研究中,观察到了堆芯破坏进程与注水质量流速或注水时间之间的一些关系。此外,通过比较测得的数据(例如,反应堆容器和干井的压力),可以估算实际注入水的流速和裂变产物的释放程度。这项研究使用了MELCOR 2.1。

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