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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:考虑到核心碎片流动路径的福岛DAI-ICHII核电站SAMPSON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日大东日本地震和海啸标志着福岛戴 - 伊赫(1F)核电站的核事故开始。评估核心地位和核心碎片的位置对于平稳执行1F退役项目非常重要。在本文中,首先通过使用Sampson的熔融核心重定位分析模块分析XR2-1实验,首先研究来自核心到下增压孔的碎屑流动路径。该研究表明,控制杆区域中的熔融材料可能积聚在速度限制器上。此外,燃料杆区域中的熔融金属的一部分直接通过入口孔口落入下限。基于这些观察结果修饰了系统计算的MCRA点燃,并进行了1F单元1中的事故进展分析。超过96wt%的核心碎片迁移到下层增压室是修饰计算中的颗粒碎片。在先前计算中出现的燃料/金属熔融相,其中在核心板位置保留核心碎片位置并未出现在修改的计算中。由于核心碎片特别是UO_2主要从入口孔口落入下层压力孔,因此在控制杆引导管等外部发生芯碎片和结构之间的热相互作用。建议使用BWR特定的实验和更详细的实验进行分析以解决RPV底部失败的不确定性。

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