首页> 外文期刊>International journal of hydrogen energy >Thermalhydraulic analysis and heat transfer correlation for an intermediate heat exchanger linking a SuperGritical Water-cooled Reactor and a Copper-Ghlorine cycle for hydrogen co-generation
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Thermalhydraulic analysis and heat transfer correlation for an intermediate heat exchanger linking a SuperGritical Water-cooled Reactor and a Copper-Ghlorine cycle for hydrogen co-generation

机译:中间热交换器的热工水力分析和传热相关性,该中间热交换器将超临界水冷反应堆与铜-精制循环连接起来进行氢气联产

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This paper presents the development of a new heat-transfer correlation for the flow of Supercritical Water (SCW) in bare circular tubes, and its applicability to thermalhydraulic analysis for Heat exchanger (HX) designs, linking a Supercritical Water-cooled nuclear Reactor (SCWR) and a Copper-Chlorine (Cu-Cl) cycle-based hydrogen co-generation facility. A large set of experimental data, obtained in SCW flowing upwards in a 4-m long vertical bare tube with a 10-mm Internal Diameter (ID), was analyzed. The data were collected at pressures of about 24 MPa, inlet temperatures from 320 to 350 ℃, values of mass flux ranging from 200 to 1500 kg/m~2·s and heat fluxes up to 1250 kW/m~2, for several combinations of wall and bulk-fluid temperatures that were below, at, or above the pseudocritical temperature. A dimensional analysis was conducted, using the Buckingham 77-theorem, to derive a general form of the empirical SCW heat-transfer correlation for the Nusselt number, which was finalized based on the experimental data obtained within the Normal Heat-Transfer (NHT) and Improved Heat-Transfer (IHT) regimes. The derived correlation showed the best fit for the experimental data within a wide range of flow conditions. This correlation has an uncertainty of about ±25% for Heat Transfer Coefficient (HTC) values and approximately ±15% for calculated wall temperatures. Subsequently, this correlation was used to calculate HTCs in support of preliminary thermalhydraulic calculations for HXs with SCW and SuperHeated Steam (SHS) as the operating fluids. The HXs are to be designed for integration into the No-Reheat or Single Reheat SCW Nuclear Power Plant (NPP) cycles and provide a link to support hydrogen production through the Cu-Cl cycle. Thermal energy will be transferred from the SCWR to an intermediate SHS loop operating at 5 MPa and delivered to the hydrolysis and oxygen-production process steps of the Cu-Cl cycle facility, which operates at temperatures of up to 530 ℃. The analyzed HXs are of a double-pipe, counter-flow design. Calculations involved numerical solutions to identify HX outlet flow temperatures, required pipe lengths, number of pipes for each HX unit, mass flow rates and other relevant heat transfer parameters. Various test conditions have been assessed in support of a database to determine feasible configurations for an HX design.
机译:本文介绍了超临界水(SCW)在裸露圆管中流动的新传热相关性的发展及其在热交换器(HX)设计的热工水力分析中的适用性,该研究将超临界水冷核反应堆(SCWR)连接在一起)和基于铜-氯(Cu-Cl)循环的氢气热电联产设施。分析了大量在SCW中向上流动的实验数据,其中SCW在具有10mm内径(ID)的4m长垂直裸管中向上流动。在几种组合下,数据是在大约24 MPa的压力,320至350℃的入口温度,200至1500 kg / m〜2·s的质量通量值和最高1250 kW / m〜2的热通量的条件下收集的低于,达到或高于假临界温度的壁和整体流体温度的平均值。使用Buckingham 77定理进行了尺寸分析,得出了Nusselt数的经验SCW传热相关性的一般形式,该形式根据正常传热(NHT)和改进的传热(IHT)机制。得出的相关性表明,在各种流动条件下,最适合实验数据。这种相关性对于传热系数(HTC)值具有约±25%的不确定性,对于计算出的壁温而言具有约±15%的不确定性。随后,此相关性用于计算HTC,以SCW和SuperHeated Steam(SHS)作为工作流体的HX的初步热工水力计算。 HX的设计目的是集成到不重热或单重SCW核电站(NPP)循环中,并提供一个链接来支持通过Cu-Cl循环生产氢气。热能将从SCWR传递到在5 MPa下运行的中间SHS回路,并传递到Cu-Cl循环设施的水解和制氧工艺步骤,该步骤在最高530℃的温度下运行。被分析的HX具有双管逆流设计。计算涉及数值解决方案,以识别HX出口流量温度,所需的管道长度,每个HX单元的管道数量,质量流量和其他相关的传热参数。为了支持HX设计,已经评估了各种测试条件以支持数据库。

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