首页> 外文会议>Embedded topical meeting on advances in thermal hydraulics >ANALYSIS OF ACCIDENT PROGRESSION WITH THE SAMPSON CODE IN THE FUKUSHIMA DAI-ICHI NUCLEAR POWER PLANT CONSIDERING DEBRIS FLOW PATHS FROM THE CORE
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ANALYSIS OF ACCIDENT PROGRESSION WITH THE SAMPSON CODE IN THE FUKUSHIMA DAI-ICHI NUCLEAR POWER PLANT CONSIDERING DEBRIS FLOW PATHS FROM THE CORE

机译:考虑芯核碎屑流路的福岛大一核电站中桑普森代码的事故进展分析

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The Great East Japan Earthquake and Tsunami on March 11, 2011 mark the start of the nuclear accident at the Fukushima Dai-ichi (1F) Nuclear Power Plant. Assessment of the core status and the location of core debris is very important for smooth execution of the 1F decommissioning project. In this paper, debris flow paths from the core to the lower plenum were first investigated by analysis of the XR2-1 experiment using molten core relocation analysis module of SAMPSON. The investigation showed that molten material in the control rod area was likely to accumulate on the velocity limiter. Furthermore a part of the molten metal in the fuel rod area fell directly through the inlet orifice to the lower plenum. MCRA noding for the system calculation was modified based on these observations and analysis of accident progression in 1F Unit 1 was performed. More than 96 wt% of the core debris relocated to the lower plenum was particle debris in the modified calculation. The fuel/metal molten phase that appeared in the previous calculation in which core debris was retained at the core plate location did not appear in the modified calculation. Since core debris especially UO_2 mainly fell from the inlet orifice to the lower plenum, thermal interaction between core debris and structures in the lower plenum would occur outside of the control rod guide tubes, etc. It is recommended that BWR-specific experiments and more detailed analysis be undertaken to resolve the uncertainties of the RPV bottom failure.
机译:2011年3月11日的东日本大地震和海啸标志着福岛第一核电站的核事故开始。评估核心状态和核心碎片的位置对于顺利执行1F退役项目非常重要。在本文中,首先通过使用SAMPSON的熔融岩心重定位分析模块对XR2-1实验进行分析,研究了从岩心到下部增压室的泥石流路径。调查表明,控制杆区域内的熔融材料可能会积聚在限速器上。此外,燃料棒区域中的一部分熔融金属直接通过进口孔掉落到下部气室。基于这些观察结果,对用于系统计算的MCRA点进行了修改,并在1F单元1中进行了事故进展分析。在修正的计算中,超过96 wt%的重心碎片被重新分配到下增压室,是颗粒碎片。在以前的计算中出现的燃料/金属熔融相(其中芯屑保留在芯板位置)未出现在修改的计算中。由于堆芯碎片(尤其是UO_2)主要从入口孔流到下增压室,因此,堆芯碎片与下增压室结构之间的热相互作用会在控制杆导管等外部发生。建议进行BWR专用实验,并进行更详细的说明进行分析以解决RPV底部故障的不确定性。

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