首页> 外文会议>International topical meeting on nuclear reactor thermal hydraulics >CONDENSATION HEAT TRANSFER COEFFICIENT CORRELATION BASED ON SLIP RATIO MODEL IN A HORIZONTAL HEAT EXCHANGER
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CONDENSATION HEAT TRANSFER COEFFICIENT CORRELATION BASED ON SLIP RATIO MODEL IN A HORIZONTAL HEAT EXCHANGER

机译:基于滑动比模型的水平换热器冷凝水传热系数相关

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Over the past few decades, there have been many experimental and analytical researches for predicting the horizontal condensation heat transfer and numerous models have been proposed. However, the proposed models that were based on the limited database, showed a considerable deviation against the experimental data, depending on authors, working fluids and flow conditions. Furthermore, since the PAFS (Passive Auxiliary Feedwater System) is a unique passive safety system adopted in the APR+ (Advanced Power Reactor Plus), conventional models showed inaccurate prediction capability on the condensation heat transfer coefficient. Experimental investigation of the condensation heat transfer and natural convection phenomena in the PAFS was experimentally investigated at KAERI (Korea Atomic Energy Research Institute). It was found that a thermal hydraulic system analysis code, MARS-KS (Multi-dimensional Analysis of Reactor Safety), underestimated the condensation heat transfer coefficient compared to the experimental data. The current study suggested a condensation heat transfer coefficient correlation using the slip ratio to model the heat transfer phenomenon inside the horizontal condensation heat exchanger. In this study, the modified correlation using the analytic slip ratio model was evaluated with the experimental data. The proposed model showed an improved prediction performance having around 8% of the error. To increase the prediction capability of the condensation heat transfer coefficient correlations developed in this study, more experimental data in the wide ranges should be compared as the further study.
机译:在过去的几十年中,已经进行了许多用于预测水平冷凝水传热的实验和分析研究,并且已经提出了许多模型。但是,根据作者,工作流体和流动条件的不同,所提出的基于有限数据库的模型显示出与实验数据相当大的偏差。此外,由于PAFS(被动辅助给水系统)是APR +(先进动力反应堆Plus)采用的独特被动安全系统,因此常规模型对冷凝传热系数的预测能力不准确。在KAERI(韩国原子能研究所)对PAFS中的凝结传热和自然对流现象进行了实验研究。结果发现,与实验数据相比,热工液压系统分析代码MARS-KS(反应堆安全性的多维分析)低估了冷凝传热系数。当前的研究提出了一种利用滑移率的冷凝传热系数相关性,以对水平冷凝换热器内部的传热现象进行建模。在这项研究中,使用实验滑移率模型对修正的相关性进行了评估。所提出的模型显示出改进的预测性能,具有大约8%的误差。为了提高本研究开发的冷凝传热系数相关性的预测能力,应将更多的实验数据在较宽的范围内进行比较,作为进一步的研究。

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