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首页> 外文期刊>International Journal of Heat and Mass Transfer >Critical heat flux (CHF) for water flow in tubes--I. Compilation and assessment of world CHF data
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Critical heat flux (CHF) for water flow in tubes--I. Compilation and assessment of world CHF data

机译：管中水的临界热通量（CHF）-I。世界CHF数据的汇编和评估

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摘要

The nuclear and conventional power industries have spent enormous resources during the past fifty years investigating the critical heat flux (CHF) phenomenon for a multitude of pool and flow boiling configurations. Experimental CHF data form the basis for the development of correlations and mechanistic models and comparison with them is the sole criterion for a reliable assessment of a correlation or model. However, experimental CHF data are rarely published, remaining in the archives of the authors or in obscure technical reports of an organization. The Purdue University-Boiling and Two-Phase Flow Laboratory (PU-BTPFL) CHF database for water flow in a uniformly heated tube was compiled from the world literature dating back to l949 and represents the largest CHF database ever assembled with 32,544 data points from over l00 sources. The superiority of this database was proven via a detailed examination of previous databases. A point-by-point assessment of the PU-BTPFL CHF database revealed that 7/100 of the data were unacceptable mainly because these data were unreliable according to the original authors of the data, unknowingly duplicated, or in violation of an energy balance. Parametric ranges of the 30,398 acceptable CHF data were diameters from 0.25 to 44.7 mm, length-to-diameter ratios from l.7 to 2484, mass velocities from l0 to l34,000 kg m~-2 s~-1, pressures from 0.7 to 2l8 bars, in1et subcoolings from 0 to 347deg.C, inlet qualities from --3.00 to 0.00, outlet subcoolings from 0 to 305deg.C, outlet qualities from --2.25 to l.00, and critical heat fluxes from 0.05 x l0~6 to 276 x l0~6 W m~-2. An examination of the parametric distribution of data within the database identified diameters less than 5 mm, mass velocities greater than l0,000 kg m~-2 s~-1, and inlet qualities below-l.0 as those experimental conditions which at present have relatively little CHF data. The combination of these conditions most likely results in subcooled CHF conditions and relatively high CHF values. The PU-BTPFL CHF database is an invaluable tool for the development of CHF correlations and mechanistic models that are superior to existing ones developed with smaller, less comprehensive CHF databases.
机译：在过去的五十年中，核能和常规电力行业花费了大量资源来研究多种池和流沸腾结构的临界热通量（CHF）现象。实验性CHF数据构成了相关性和机理模型开发的基础，与它们进行比较是对相关性或模型进行可靠评估的唯一标准。但是，实验性CHF数据很少发布，保留在作者的档案中或组织的晦涩的技术报告中。普渡大学沸腾和两相流实验室（PU-BTPFL）均匀加热管中水流的CHF数据库是根据可追溯至1949年的世界文献编制的，代表了迄今为止最大的CHF数据库，包含来自32个以上的34544个数据点100个来源。该数据库的优越性已通过对先前数据库的详细检查得到证明。对PU-BTPFL CHF数据库进行的逐点评估显示，不接受7/100的数据，主要是因为这些数据的原始作者认为这些数据不可靠，无意识地重复或违反了能量平衡。 30,398个可接受的CHF数据的参数范围是直径从0.25到44.7 mm，长径比从1.7到2484，质量速度从10到134000 kg m〜-2 s〜-1，压力从0.7到2l8 bar，输入过冷度从0到347°C，入口质量从--3.00到0.00，出口过冷度从0到305°C，出口质量从--2.25到1.00，临界热通量从0.05 x l0 〜6至276 x l0〜6 W m〜-2。对数据库中数据的参数分布的检查确定了直径小于5 mm，质量速度大于10 000 kg m〜-2 s-1以及入口质量小于1.0.0是目前的实验条件CHF数据相对较少。这些条件的组合很可能导致过冷的CHF条件和相对较高的CHF值。 PU-BTPFL CHF数据库是开发CHF相关性和机制模型的宝贵工具，优于使用较小，较不全面的CHF数据库开发的现有模型。

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