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Validation and application of the MEWA code to analysis of debris bed coolability

机译:验证并应用MEWA代码分析碎屑床的可冷却性

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This paper was first aimed at validating the MEWA code against experiments for two-phase flow and dryout in particulate beds, and then investigating the coolability of ex-vessel debris beds with cylindrical, conical and truncated conical shapes assumed to form under severe accident scenarios of a boiling water reactor. The validation was mainly performed against the POMECO-FL and POMECO-HT experiments carried out at KTH for investigating frictional laws and coolability limit (dryout) of particulate beds, respectively. The comparison of the experimental and numerical results shows that the MEWA code is capable of predicting both the pressure drop of two-phase flow through porous media and the dryout condition of various stratified beds. While the coolability of a one-dimensional homogeneous debris bed is bounded by counter-current flow limit (CCFL), the coolability of a heap-like debris bed can be improved due to lateral ingression of coolant in a multi-dimensional geometry. The simulations showed that the dryout power density of a prototypical debris bed was roughly inversely proportional to the bed's height regardless of the bed's shape. The impacts of a debris bed's features on coolability are manifested in three aspects: multidimensionality and contour surface area of the bed, as well as the uniformity of its shape. The contour surface area is defined as the interface between debris bed and water pool, and its effective value depends on the surface orientation that determines the amount of water ingress and vapor escape. The perfect uniformity in bed's shape as cylindrical bed results in even distributions of temperature and void fraction. The dryout power density was also predicted to be strongly correlated to the uniformity of bed's shape. The MEWA simulation also predicted that coolability was improved by an downcomer embedded in the center of debris bed. The efficiency of such enhancement was largely determined by the downcomer's length, whose optimal value was obtained in simulation.
机译:本文首先旨在针对颗粒床中两相流动和变干的实验验证MEWA规范,然后研究假定在严重事故场景下形成的圆柱形,圆锥形和截头圆锥形的前容器碎片床的可冷却性。沸水反应堆验证主要针对在KTH进行的POMECO-FL和POMECO-HT实验进行,分别用于调查颗粒床的摩擦规律和可冷却性极限(变干)。实验和数值结果的比较表明,MEWA代码既可以预测通过多孔介质的两相流的压降,又可以预测各种分层床的干燥条件。虽然一维均质碎屑床的可冷却性受到逆流限制(CCFL)的限制,但由于冷却液在多维几何形状中的横向侵入,可以提高堆状碎屑床的可冷却性。模拟表明,原型碎片床的干透功率密度与床的高度大致成反比,而与床的形状无关。杂物床特征对可冷却性的影响体现在三个方面:床的多维性和轮廓表面积以及形状的均匀性。轮廓表面积定义为碎片床与水池之间的界面,其有效值取决于确定水进入量和蒸汽逸出量的表面方向。作为圆柱床的床形状的完美均匀性导致温度和空隙率的均匀分布。干燥功率密度也被预测与床形状的均匀性密切相关。 MEWA模拟还预测,通过嵌入碎屑床中心的降液管可以改善可冷却性。这种增强的效率很大程度上取决于降液管的长度,降液管的长度是通过仿真获得的。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2018年第2期|22-37|共16页
  • 作者

    Huang Zheng; Ma Weimin;

  • 作者单位

    Royal Inst Technol KTH, Div Nucl Power Safety, Roslagstullsbacken 21, S-10691 Stockholm, Sweden;

    Royal Inst Technol KTH, Div Nucl Power Safety, Roslagstullsbacken 21, S-10691 Stockholm, Sweden;

  • 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
  • 中图分类
  • 关键词

  • 入库时间 2022-08-18 00:40:42

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