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首页> 外文期刊>Nuclear Engineering and Design >Validation of intermediate heat and decay heat exchanger model in MARS-LMR with STELLA-1 and JOYO tests
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Validation of intermediate heat and decay heat exchanger model in MARS-LMR with STELLA-1 and JOYO tests

机译:使用STELLA-1和JOYO测试验证MARS-LMR中的中间热量和衰减热交换器模型

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摘要

The MARS-LMR code has been developed by the Korea Atomic Energy Research Institute (KAERI) to analyze transients in a pool-type sodium-cooled fast reactor (SFR). Currently, KAERI is developing a prototype Gen-IV SFR (PGSFR) with metallic fuel. The decay heat exchangers (DHXs) and the intermediate heat exchangers (IHXs) were designed as a sodium-sodium counter-flow tube bundle type for decay heat removal system (DHRS) and intermediate heat transport system (IHTS), respectively. The IHX and DHX are important components for a heat removal function under normal and accident conditions, respectively. Therefore, sodium heat transfer models for the DHX and IHX heat exchangers were added in MARS-LMR. In order to validate the newly added heat transfer model, experimental data were obtained from the JOYO and STELLA-1 facilities were analyzed. JOYO has two different types of IHXs: type-A (co-axial circular arrangement) and type-B (triangular arrangement). For the code validation, 38 and 39 data points for type A and type B were selected, respectively. A DHX performance test was conducted in STELLA-1, which is the test facility for heat exchangers and primary pump in the PGSFR. The DHX test in STELLA-1 provided eight data points for a code validation. Ten nodes are used in the heat transfer region is used, based on the verification test for the heat transfer models. RMS errors for JOYO IHX type A and type B of 19.1% and 4.3% are obtained, respectively. It was reported that a bypass flow of 20% was allowed in type A test. When the bypass flow model was added to MARS-LMR, the RMS error for type A reduced to 12.6%. The RMS error for the STELLA-1 DHX was estimated to be 3.5%. Through the comparative studies with various alternative heat transfer models in the tube and shell-side, the base heat transfer model in MARS-LMR was found to give good prediction for the STELLA-1 and JOYO experiment results. (C) 2016 Elsevier B.V. All rights reserved.
机译:MARS-LMR代码是由韩国原子能研究院(KAERI)开发的,用于分析池式钠冷快堆(SFR)中的瞬态。目前,KAERI正在开发具有金属燃料的Gen-IV SFR(PGSFR)原型。衰变热交换器(DHXs)和中间热交换器(IHXs)分别设计为衰变除热系统(DHRS)和中间传热系统(IHTS)的钠-钠逆流管束式。 IHX和DHX分别是正常和事故情况下排热功能的重要组件。因此,在MARS-LMR中添加了DHX和IHX热交换器的钠热传递模型。为了验证新增加的传热模型,从JOYO和STELLA-1设施获得了实验数据。 JOYO具有两种不同类型的IHX:A型(同轴圆形排列)和B型(三角形排列)。为了进行代码验证,分别选择了类型A和类型B的38和39个数据点。在STELLA-1中进行了DHX性能测试,STELLA-1是PGSFR中用于热交换器和主泵的测试设备。 STELLA-1中的DHX测试提供了八个数据点用于代码验证。基于传热模型的验证测试,在传热区域中使用了十个节点。 JOYO IHX A型和B型的RMS误差分别为19.1%和4.3%。据报道,在A型测试中允许20%的旁路流量。当将旁路流模型添加到MARS-LMR时,A型的RMS误差降低到12.6%。 STELLA-1 DHX的RMS误差估计为3.5%。通过在管和壳侧使用各种替代传热模型的比较研究,发现MARS-LMR中的基础传热模型可以为STELLA-1和JOYO实验结果提供良好的预测。 (C)2016 Elsevier B.V.保留所有权利。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2016年第11期|269-282|共14页
  • 作者单位

    Korea Atom Energy Res Inst, Sodium Cooled Fast Reactor Design Div, 989-111 Daedeok Daero, Taejon 305353, South Korea;

    Korea Atom Energy Res Inst, Sodium Cooled Fast Reactor Design Div, 989-111 Daedeok Daero, Taejon 305353, South Korea;

    Korea Atom Energy Res Inst, Sodium Cooled Fast Reactor Design Div, 989-111 Daedeok Daero, Taejon 305353, South Korea;

    Korea Atom Energy Res Inst, Sodium Cooled Fast Reactor Design Div, 989-111 Daedeok Daero, Taejon 305353, South Korea;

    Korea Atom Energy Res Inst, Sodium Cooled Fast Reactor Design Div, 989-111 Daedeok Daero, Taejon 305353, South Korea;

    Sejong Univ, Dept Nucl Engn, 209 Neungdong Ro, Seoul 143747, South 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
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