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Experimental investigation on self-leveling behavior in debris beds

机译:杂物床中自流平行为的实验研究

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摘要

During a hypothetical core-disruptive accident in a sodium-cooled fast breeder reactor, degraded core materials can form debris beds on the core-support structure and/or in the lower inlet plenum of the reactor vessel from rapid quenching and fragmentation of core material pool. Coolant boiling may lead ultimately to leveling of the debris bed that is crucial to the relocation of molten core and heat-removal capability of the debris bed. In the present study, we elected to use depressurization boiling to simujate an axially increasing void distribution in the debris bed. Bottom-heating boiling was also chosen to confirm that characteristics of the self-leveling process do not depend on the boiling mode. Particle size (between 0.5 and 6 mm), shape (spherical and non-spherical), bed volume (between 5 and 81) and density (namely of alumina, zirconia, lead and stainless steel) along with boiling intensity and total volume were taken as experimental parameters to obtain the general characteristics of the self-leveling process. A series of experiments with simulant materials were conducted and analyzed in detail. The good concordance of the transient processes obtained from the different boiling methods sufficiently demonstrates that the present results obtained using the depressurization boiling method exhibit these general self-leveling characteristics. Detailed comparisons of deduced time variations of the inclination angle provides qualitative tendencies based on the experimental parameters considered influential to self-leveling behavior. The rationale behind the definition introduced for equivalent power density is also presented.
机译:在钠冷却的快速增殖反应堆中发生假想的堆芯破坏事故期间,降解的堆芯材料会因堆芯材料池的快速淬火和破碎而在堆芯支撑结构上和/或在反应堆容器的下部进气室中形成碎屑床。 。冷却剂沸腾可能最终导致碎屑床的整平,这对于熔融芯的重新定位和碎屑床的散热能力至关重要。在本研究中,我们选择使用降压沸腾模拟碎片床中轴向增加的孔隙分布。还选择了底部加热沸腾以确认自流平过程的特征不取决于沸腾模式。取颗粒大小(0.5至6 mm),形状(球形和非球形),床层体积(5至81之间)和密度(即氧化铝,氧化锆,铅和不锈钢)以及沸腾强度和总体积作为实验参数以获得自流平过程的一般特性。进行了一系列使用模拟材料的实验,并进行了详细分析。从不同沸腾方法获得的过渡过程的良好一致性充分证明,使用降压沸腾方法获得的当前结果显示出这些一般的自流平特性。推导的倾斜角度随时间变化的详细比较提供了基于认为对自流平行为有影响的实验参数的定性趋势。还介绍了引入等效功率密度定义背后的原理。

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  • 来源
    《Nuclear Engineering and Design》 |2011年第1期|p.366-377|共12页
  • 作者单位

    Department of Applied Quantum Physics and Nuclear Engineering, Kyushu University, 744 Moto-oka, Nishi-ku, Fukuoka 819-0395, Japan;

    Department of Applied Quantum Physics and Nuclear Engineering, Kyushu University, 744 Moto-oka, Nishi-ku, Fukuoka 819-0395, Japan;

    Department of Applied Quantum Physics and Nuclear Engineering, Kyushu University, 744 Moto-oka, Nishi-ku, Fukuoka 819-0395, Japan;

    Department of Applied Quantum Physics and Nuclear Engineering, Kyushu University, 744 Moto-oka, Nishi-ku, Fukuoka 819-0395, Japan;

    Department of Applied Quantum Physics and Nuclear Engineering, Kyushu University, 744 Moto-oka, Nishi-ku, Fukuoka 819-0395, Japan;

    Department of Applied Quantum Physics and Nuclear Engineering, Kyushu University, 744 Moto-oka, Nishi-ku, Fukuoka 819-0395, Japan;

    Advanced Nuclear System R&D Directorate, Japan Atomic Energy Agency, 4002 Narita, O-arai, Ibaraki 311 -1393, Japan;

    Advanced Nuclear System R&D Directorate, Japan Atomic Energy Agency, 4002 Narita, O-arai, Ibaraki 311 -1393, Japan;

    Advanced Nuclear System R&D Directorate, Japan Atomic Energy Agency, 4002 Narita, O-arai, Ibaraki 311 -1393, Japan;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
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  • 入库时间 2022-08-18 00:44:32

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