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EXPERIMENTAL AND COMPUTATIONAL ASSESSMENT OF CORE BYPASS FLOW IN BLOCK-TYPE VERY HIGH TEMPERATURE REACTOR

机译:块状超高温反应器堆芯旁路流动的实验和计算评估

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摘要

An accurate prediction of core bypass flow is of great importance in the design of very high temperature reactor (VHTR) cores in terms of the fuel thermal margin and safety. In the present study, a unit-cell experiment and computational fluid dynamics (CFD) analysis were carried out to evaluate the amount and distribution of core bypass flow. This study examined the effects of the inlet mass flow rate, block combinations, and thickness of the bypass gap. The prediction capability of the CFD code FLUENT was val- idated by the unit-cell experimental result. The analysis was extended to the entire core region. In this simulation, a quarter core was simulated using the nonconformal grid method to reduce the computational cost and time. The accuracy and applicability of the nonconformal grid method were assessed from the experimental results and comparative simulation. In conclusion, the flow distribution in the VHTR core was evaluated by the CFD core model with low error and computational cost.
机译:就燃料热裕度和安全性而言,准确预测堆芯旁通流量对超高温反应堆(VHTR)堆芯的设计非常重要。在本研究中,进行了单胞实验和计算流体动力学(CFD)分析,以评估岩心旁路流量的数量和分布。这项研究检查了入口质量流速,阀块组合和旁路间隙厚度的影响。 CFD代码FLUENT的预测能力已通过晶胞实验结果验证。分析扩展到整个核心区域。在此仿真中,使用非等值网格方法对四分之一核进行了仿真,以减少计算成本和时间。从实验结果和比较模拟中评估了非共形网格方法的准确性和适用性。综上所述,通过CFD堆芯模型评估了VHTR堆芯中的流量分布,且误差低且计算成本低。

著录项

  • 来源
    《Nuclear Technology》 |2011年第2期|p.419-434|共16页
  • 作者单位

    Seoul National University, Department of Nuclear Engineering 130 dong, San 56-1, Daehak-dong, Kwanak-gu, Seoul 151-742, Korea;

    Seoul National University, Department of Nuclear Engineering 130 dong, San 56-1, Daehak-dong, Kwanak-gu, Seoul 151-742, Korea;

    Korea Atomic Energy Research Institute, 150-1 Deokjin-Dong 1045 Daedeokdaero, Yuseong, Daejeon 305-353, Korea;

    Seoul National University, Department of Nuclear Engineering 130 dong, San 56-1, Daehak-dong, Kwanak-gu, Seoul 151-742, Korea;

  • 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

    core bypass flow; very high temperature reactor; prismatic core;

    机译:核心旁路流量;高温反应堆;棱柱形芯;

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