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Experimental and theoretical study of horizontal tube bundle for passive condensation heat transfer.

机译:水平管束被动冷凝传热的实验和理论研究。

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摘要

The research in this thesis supports the design of a horizontal tube bundle condenser for passive heat removal system in nuclear reactors. From nuclear power plant containment, condensation of steam from a steam/noncondensable gas occurs on the primary side and boiling occurs on the secondary side; thus, heat exchanger modeling is a challenge.; For the purpose of this experimental study, a six-tube bundle is used, where the outer diameter, inner diameter, and length of each stainless steel tube measures 38.10mm (1.5 inches), 31.75mm (1.25 inches) and 3.96m (156 inches), respectively. The pitch to diameter ratio was determined based on information gathered from literature surveys, and the dimensions were determined from calculations and experimental data. The objective of the calculations, correlations, and experimental data was to obtain complete condensation within the tube bundle.; Experimental conditions for the tests in this thesis work were determined from Design Basis Accident (DBA). The applications are for an actual Passive Containment Cooling Systems (PCCS) condenser under postulated accident conditions in future light water reactors.; In this research, steady state and transient experiments were performed to investigate the effect of noncondensable gas on steam condensation inside and boiling outside a tube bundle heat exchanger. The condenser tube inlet steam mass flow rate varied from 18.0 to 48.0 g/s, the inlet pressure varied from 100 kPa to 400 kPa, and the inlet noncondensable gas mass fraction varied from 1% to 10%. The effect of the noncondensable gas was examined by comparing the tube centerline temperatures for various inlet and system conditions. As a result, it was determined that the noncondensable gas accumulated near the condensate film causing a decrease of mass and energy transfer.; In addition, the effect of the inlet steam flow rate gas was investigated by comparing the tube centerline temperatures, the conclusion being that, as the inlet steam mass flow rate increased, the length required for complete condensation also increased. Comparison of tube centerline temperature profiles was also used to examine the effect of inlet pressure on the heat transfer performance. From this assessment, it was determined that as the inlet pressure increased, the length required for complete condensation decreased.; The investigation of tube bundle effects was conducted by comparing the condensate flow rates. The experimental results showed that the upper tubes in the bundle had better heat transfer performance than the lower tubes.; In regard to modeling of the heat exchanger in this study, for the primary side, an empirical correlation was developed herein to provide Nusselt numbers for condensation heat transfer in horizontal tubes with noncondensable gases. Nusselt numbers were correlated as: Nu = 106.31·Re m0.147·W a-0.843. The empirical model for condensation heat transfer coefficients and the secondary-side model were integrated within a Matlab program to provide an analysis tool for horizontal tube bundle condenser heat exchangers. Also on the secondary side, two phase heat transfer coefficients were modeled considering both convective boiling and nucleate boiling as: hTP = 10.03·exp(-2.28·alpha)· hCV + 0.076·exp[3.73x10-6·(Re f-1.6x105)]·hNB.
机译:本文的研究为核反应堆被动排热系统的卧式管束冷凝器的设计提供了支持。在核电厂的安全壳内,蒸汽/不可冷凝气体中的蒸汽凝结在一次侧发生,沸腾在次侧发生;因此,换热器建模是一个挑战。为了进行本实验研究,使用了六管束,其中每根不锈钢管的外径,内径和长度分别为38.10mm(1.5英寸),31.75mm(1.25英寸)和3.96m(156)英寸)。螺距与直径之比是根据文献调查得出的信息确定的,尺寸是根据计算和实验数据确定的。计算,相关性和实验数据的目的是获得管束内的完全冷凝。本文的测试条件是根据设计基准事故(DBA)确定的。这些应用是在未来的轻水反应堆中,在假定的事故条件下,用于实际的被动安全壳冷却系统(PCCS)冷凝器。在这项研究中,进行了稳态和瞬态实验,以研究不可冷凝气体对管束式换热器内部和外部沸腾的影响。冷凝器管的入口蒸汽质量流量在18.0至48.0 g / s之间变化,入口压力在100 kPa至400 kPa之间变化,入口不可凝气体质量分数在1%至10%之间变化。通过比较各种进气口和系统条件下的管道中心线温度,检查了不可冷凝气体的影响。结果,确定了在冷凝膜附近聚集的不可冷凝气体引起质量和能量传递的降低。另外,通过比较管中心线温度来研究入口蒸汽流量气体的影响,结论是,随着入口蒸汽质量流量的增加,完全冷凝所需的长度也增加了。管中心线温度曲线的比较还用于检查入口压力对传热性能的影响。根据该评估,确定随着入口压力的增加,完全冷凝所需的长度减少。通过比较冷凝水流量来研究管束效应。实验结果表明,管束中的上管比下管具有更好的传热性能。关于该研究中的热交换器的建模,对于一次侧,本文开发了经验相关性,以提供用于具有不可冷凝气体的水平管中的冷凝热传递的努塞尔数。 Nusselt数关联为:Nu = 106.31·Re m0.147·W a-0.843。在Matlab程序中集成了冷凝传热系数的经验模型和次级模型,为水平管束冷凝器换热器提供了分析工具。同样在次级侧,考虑到对流沸腾和成核沸腾,对两相传热系数进行建模:hTP = 10.03·exp(-2.28·alpha)·hCV + 0.076·exp [3.73x10-6·(Re f-1.6 x105)]·hNB。

著录项

  • 作者

    Song, Yong Jae.;

  • 作者单位

    Purdue University.$bNuclear Engineering.;

  • 授予单位 Purdue University.$bNuclear Engineering.;
  • 学科 Engineering Nuclear.
  • 学位 Ph.D.
  • 年度 2007
  • 页码 309 p.
  • 总页数 309
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类 原子能技术;
  • 关键词

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