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Transient LOFA computations for a VHTR using one-twelfth core flow models

机译:使用十二分之一核心流模型的VHTR的瞬时LOFA计算

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摘要

A prismatic gas-cooled very high temperature reactor (VHTR) is being developed under the next generation nuclear program. One of the concerns for the reactor design is the effects of a loss of flow accident (LOFA) where the coolant circulators are lost for some reason, causing a loss of forced coolant flow through the core. In the previous studies, the natural circulation in the whole reactor vessel (RV) was obtained by segmentation strategies if the computational fluid dynamic (CFD) analysis with a sufficiently refined mesh was conducted, due to the limits of computer capability. The computational domains in the previous studies were segmented sections which were small flow region models, such as 1/12 sectors, or a combination of a few number of the 1/12 sector (ranging from 2 to 15) using geometric symmetry, for a full dome region. The present paper investigates the flow and heat transfer for a much larger flow region model, a 1/12 core model, using high performance computing. The computation meshes for 1/12 sector and 1/12 reactor core are of 7.8 M and similar to 531 M, respectively. Over 85,000 and 35,000 iterations for steady and transient (100 s) calculations are required to achieve convergence, respectively. similar to 0.1 min CPU time was required using 192 computer cores for the 1/12 sector model and similar to 1.3 min CPU time using 768 cores in parallel for the 1/12 core model, for every iteration, using ALPS, Advanced Large-scale Parallel Superclusters.
机译:根据下一代核计划,正在开发棱柱形气冷超高温反应堆(VHTR)。反应堆设计的关注点之一是失流事故(LOFA)的影响,在该事故中冷却剂循环器由于某种原因而丢失,从而导致强制性冷却剂流经堆芯的损失。在先前的研究中,由于计算机能力的限制,如果使用足够精细的网格进行计算流体动力学(CFD)分析,则通过分段策略可以获得整个反应堆容器(RV)的自然循环。在先前的研究中,计算域是分段截面,这些截面截面是小流动区域模型,例如1/12扇形,或者使用几何对称性将一部分的1/12扇形(从2到15)组合在一起,用于完整的圆顶区域。本文使用高性能计算研究了更大的流动区域模型(1/12核心模型)的流动和传热。 1/12扇区和1/12反应堆堆芯的计算网格分别为7.8 M和531M。要实现收敛,分别需要进行稳定和瞬态(100 s)计算的85,000和35,000次迭代。对于1/12扇区模型,使用192个计算机内核需要大约0.1分钟的CPU时间,对于1/12内核模型,使用768个并行内核需要1.3分钟的CPU时间,对于每次迭代,使用ALPS(高级大规模)并行超级集群。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2016年第5期|89-100|共12页
  • 作者单位

    Natl Tsing Hua Univ, Inst Nucl Engn & Sci, Hsinchu, Taiwan;

    Natl Tsing Hua Univ, Inst Nucl Engn & Sci, Hsinchu, Taiwan;

    Idaho Natl Lab, Idaho Falls, ID USA;

    City Univ Hong Kong, Dept Mech & Biomed Engn, Kowloon, Hong Kong, Peoples R China;

  • 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 00:41:47

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