管内流动沸腾CHF实验及氟里昂模化研究  

Study of Critical Heat Flux Experiments in an Uniformly Heated Tube Cooled by Water and Freon-Water Modelling

作　　者：陈炳德[1] 

机构地区：[1]中国核动力研究设计院

出　　处：《核动力工程》1994年第5期460-464,共5页Nuclear Power Engineering

摘　　要：在高温高压实验回路上进行了水在竖直管内向上流动的临界热流密度（ＣＨＦ）实验研究。共获得１１７组数据，实验参数为：压力ｐ＝６．３７～１４．７ＭＰａ；质量流速ｗ＝５７１～５４６６ｋｇ／ｍ２·ｓ，进口欠热度△ｈｉ＝９６～７４４ｋＪ／ｋｇ；出口含汽ｘｃ＝－０．０９４～０．７０２．用数学回归整理成经验关系式。该式与实验数据的总均方根偏差为５．３３％．同时，将Ａｈｍａｄ和张振杰氟里昂与水模化转换因子在应用范围内作了一些数学处理，实现了计算机快速双向模化转换，并用氟里昂和水的ＣＨＦ数据对上述两种模化方法进行了验证．结果表明，这两种模化方法都能较好地模拟单通道内水和氟里昂竖直向上流动沸腾的ＣＨＦ现象．其总均方根偏差在１０％以内。在本实验参数范围内，张振杰模化结果在数据分布和均方根偏差上稍优于Ａｈｍａｄ法．The critical heat flux (CHF) experiments have been done with an uniformly heated tubecooled by water in large parameter range in the high pressure and high temperature test loop ofReactor Thermohydraulic Laboratory in NPIC. Total 117 set CHF data is obtained with pressur 6.37-14.7MPa, mass flux 571-5466 kg/m2. s, inlet subcooling 96-744kJ/kg andcritical quality-0. 094-0. 702. An expirical corrlation is derived by mean Square regression.The rms of comparison of predicted CHF by the correlation with the experimental CHF is 5. 33%, Forthermore, a set of freon-water CHF transformation formulas based on Ahmad andZhang freon-water CHF modelling factors are set up in order to chang freon CHF to waterand /or in reverse quickly and easyly. The Ahmad and Zhang modelling methods have beencompared with experimental data. The'results show both of them can describe the CHF phenomena of freon and water in a vertical uniformly heated tube. The rms 9. 87% and 8. 44%, respectively, indicate that Zhang modelling factor is a litter better in this experimental Parameter range.

关 键 词：临界热流密度 水 氟里昂 模化 

分 类 号：TL333[核科学技术—核技术及应用]