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Assessment of horizontal in-tube condensation models using MARS code. Part I: Stratified flow condensation

机译:使用MARS代码评估水平管内冷凝模型。第一部分:分层流冷凝

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摘要

The accurate prediction of the horizontal in-tube condensation heat transfer is a primary concern in the optimum design and safety analysis of horizontal heat exchangers of passive safety systems such as the passive containment cooling system (PCCS), the emergency condenser system (ECS) and the passive auxiliary feed-water system (PAFS). It is essential to analyze and assess the predictive capability of the previous horizontal in-tube condensation models for each flow regime using various experimental data. This study assessed totally 11 condensation models for the stratified flow, one of the main flow regime encountered in the horizontal condenser, with the heat transfer data from the Purdue-PCCS experiment using the multi-dimensional analysis of reactor safety (MARS) code. From the assessments, it was found that the models by Akers and Rosson, Chato, Tandon et al., Sweeney and Chato, and Cavallini et al. (2002) under-predicted the data in the main condensation heat transfer region, on the contrary to this, the models by Rosson and Meyers, Jaster and Kosky, Fujii, Dobson and Chato, and Thome et al. similarly- or over-predicted the data, and especially, Cavallini et al. (2006) model shows good predictive capability for all test conditions. The results of this study can be used importantly to improve the condensation models in thermal hydraulic code, such as RELAP5 or MARS code.
机译:水平管内冷凝热传递的准确预测是被动安全系统(例如被动安全壳冷却系统(PCCS),应急冷凝器系统(ECS)和无源安全系统)的水平热交换器的最佳设计和安全分析的主要考虑因素。被动辅助给水系统(PAFS)。必须使用各种实验数据来分析和评估以前的水平管内冷凝模型对每种流态的预测能力。这项研究使用反应堆安全(MARS)程序的多维分析,利用来自Purdue-PCCS实验的传热数据,评估了分层流(水平冷凝器中遇到的主要流态之一)的总共11个冷凝模型。从评估中发现,Akers和Rosson,Chato,Tandon等人,Sweeney和Chato和Cavallini等人的模型。 (2002年)对主要凝结传热区域的数据预测不足,相反,Rosson和Meyers,Jaster和Kosky,Fujii,Dobson和Chato以及Thome等人的模型与此相反。类似或过度预测的数据,尤其是Cavallini等。 (2006)模型显示了对所有测试条件的良好预测能力。这项研究的结果可用于改进热力水力代码(例如RELAP5或MARS代码)中的冷凝模型。

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  • 来源
    《Nuclear Engineering and Design》 |2013年第1期|254-265|共12页
  • 作者单位

    Department of Engineering Project, FNC Technology Co., Ltd., Bldg 135-308, Seoul National University, Gwanak-gu, Seoul 151-744, Republic of Korea,Department of Nuclear Engineering, Seoul National University, Gwanak-gu, Seoul 151-744, Republic of Korea;

    Department of Engineering Project, FNC Technology Co., Ltd., Bldg 135-308, Seoul National University, Gwanak-gu, Seoul 151-744, Republic of Korea;

    Korea Institute of Nuclear Safety, 19 Kuseong-dong, Yuseong-gu, Daejon, Republic of Korea;

    Korea Institute of Nuclear Safety, 19 Kuseong-dong, Yuseong-gu, Daejon, Republic of Korea;

    Department of Nuclear Engineering, Seoul National University, Gwanak-gu, Seoul 151-744, Republic of 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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