首页> 外文期刊>Nuclear Technology >Development of Heat Transfer Model Package for Horizontal U-Shaped Heat Exchanger Submerged in Pool of Passive Safety System
【24h】

Development of Heat Transfer Model Package for Horizontal U-Shaped Heat Exchanger Submerged in Pool of Passive Safety System

机译:潜入被动安全系统池中的水平U形热交换器的传热模型套件的开发

获取原文
获取原文并翻译 | 示例
           

摘要

A horizontal U-shaped heat exchanger (HX) submerged in a pool is under development as a piece of key equipment for a passive safety system in a nuclear power plant (NPP). For the successful design of the HX and the safety analysis of the NPP, reliable prediction of the heat transfer performance of the HX is important. At present, the design and the safety analysis of the passive safety systems are performed mainly using best-estimate thermal-hydraulic analysis codes such as RELAP5 and MARS. However, those codes do not have suitable models for both condensation heat transfer in the horizontal tube and natural convective and nucleate boiling heat transfer on the horizontal tube, both of which ultimately determine the heat transfer performance of the HX. This study developed a heat transfer model package for the horizontal U-shaped HX submerged in a pool by improving the horizontal in-tube condensation model and developing the out-tube natural convective and nucleate boiling model. From the validation results, the proposed model provides an improved prediction of HX performance (condensation, natural convection and nucleate boiling, and heat removal rate of the HX) compared to the default model in MARS.
机译:浸入池中的水平U形热交换器(HX)正在开发中,作为核电站(NPP)中被动安全系统的关键设备。对于HX的成功设计和NPP的安全性分析,可靠预测HX的传热性能非常重要。目前,被动安全系统的设计和安全分析主要使用最佳估计的热工液压分析代码,例如RELAP5和MARS。但是,这些代码对于水平管中的冷凝传热以及水平管中的自然对流和成核沸腾沸腾传热都没有合适的模型,这两者最终决定了HX的传热性能。本研究通过改进水平管内冷凝模型并开发管外自然对流和成核沸腾模型,开发了用于淹没在池中的水平U形HX的传热模型包。从验证结果来看,与MARS中的默认模型相比,所提出的模型可以更好地预测HX的性能(冷凝,自然对流和核沸腾以及HX的除热率)。

著录项

  • 来源
    《Nuclear Technology》 |2016年第2期|303-318|共16页
  • 作者单位

    FNC Technology Company, Ltd., Department of Nuclear Thermal-Hydraulic Research, 46, Tapsil-ro, Giheung-gu, Yongin-si, Gyeonggi-do, 446-902, Korea;

    FNC Technology Company, Ltd., Department of Nuclear Thermal-Hydraulic Research, 46, Tapsil-ro, Giheung-gu, Yongin-si, Gyeonggi-do, 446-902, Korea;

    Seoul National University, Department of Nuclear Engineering, Gwanak-gu, Seoul 151-742, Korea;

    Seoul National University, Department of Nuclear Engineering, Gwanak-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

    Passive safety system; MARS; heat transfer model package;

    机译:被动安全系统;火星;传热模型包;

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱:kefu@zhangqiaokeyan.com

京公网安备:11010802029741号 ICP备案号:京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有
  • 客服微信

  • 服务号