{"title":"垂直圆管池沸腾气泡行为及临界热流密度的实验分析","authors":"Bikash Pattanayak, Hardik B. Kothadia","doi":"10.1115/1.4063041","DOIUrl":null,"url":null,"abstract":"\n The heat transfer during pool boiling incorporates a higher rate of heat dissipation capability at low-temperature differences. This technique is widely used in the nuclear industry for thermal management. In this study, the effect of tube diameter and length on critical heat flux (CHF) at atmospheric conditions in saturated water during pool boiling is analyzed. The tubes of SS 304 are kept in the vertical orientation. The diameter of the tubes ranges from 1.2 mm to 9 mm. The tube lengths varying from 50mm to 1000mm. It has been noted that tubes of smaller diameter show a greater magnitude of CHF for the given length. For a given diameter, a longer tube is found to have lower CHF than the ones having lesser length. The variation in the CHF magnitude is negligible for tubes with a diameter of more than 2.5 mm beyond a length of 200 mm. The location of occurrence of CHF is near the bottom end of the vertical tube. The study illustrates the behavior of bubble nucleation for various tube dimensions and heat fluxes. The inception and detachment of bubbles for different tubes are analyzed. The pool boiling regime is categorized and studied basing the behaviour of the incepted and departed bubble. A mathematical relation that empirically accounts for the effect of tube dimensions i.e. length and diameter on pool boiling CHF is proposed. The experimental CHF data obtained during pool boiling are tabulated towards contributing to the CHF databank.","PeriodicalId":16756,"journal":{"name":"Journal of Nuclear Engineering and Radiation Science","volume":"31 1","pages":""},"PeriodicalIF":0.5000,"publicationDate":"2023-07-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"1","resultStr":"{\"title\":\"Experimental Analysis Of Bubble Behavior And Critical Heat Flux During Pool Boiling On Vertical Circular Tubes\",\"authors\":\"Bikash Pattanayak, Hardik B. Kothadia\",\"doi\":\"10.1115/1.4063041\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"\\n The heat transfer during pool boiling incorporates a higher rate of heat dissipation capability at low-temperature differences. This technique is widely used in the nuclear industry for thermal management. In this study, the effect of tube diameter and length on critical heat flux (CHF) at atmospheric conditions in saturated water during pool boiling is analyzed. The tubes of SS 304 are kept in the vertical orientation. The diameter of the tubes ranges from 1.2 mm to 9 mm. The tube lengths varying from 50mm to 1000mm. It has been noted that tubes of smaller diameter show a greater magnitude of CHF for the given length. For a given diameter, a longer tube is found to have lower CHF than the ones having lesser length. The variation in the CHF magnitude is negligible for tubes with a diameter of more than 2.5 mm beyond a length of 200 mm. The location of occurrence of CHF is near the bottom end of the vertical tube. The study illustrates the behavior of bubble nucleation for various tube dimensions and heat fluxes. The inception and detachment of bubbles for different tubes are analyzed. The pool boiling regime is categorized and studied basing the behaviour of the incepted and departed bubble. A mathematical relation that empirically accounts for the effect of tube dimensions i.e. length and diameter on pool boiling CHF is proposed. The experimental CHF data obtained during pool boiling are tabulated towards contributing to the CHF databank.\",\"PeriodicalId\":16756,\"journal\":{\"name\":\"Journal of Nuclear Engineering and Radiation Science\",\"volume\":\"31 1\",\"pages\":\"\"},\"PeriodicalIF\":0.5000,\"publicationDate\":\"2023-07-25\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"1\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Journal of Nuclear Engineering and Radiation Science\",\"FirstCategoryId\":\"1085\",\"ListUrlMain\":\"https://doi.org/10.1115/1.4063041\",\"RegionNum\":0,\"RegionCategory\":null,\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"Q4\",\"JCRName\":\"NUCLEAR SCIENCE & TECHNOLOGY\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Journal of Nuclear Engineering and Radiation Science","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.1115/1.4063041","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q4","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 1
摘要
池沸腾过程中的传热在低温差下具有较高的散热能力。该技术广泛应用于核工业的热管理。本文分析了常压条件下饱和水池沸腾过程中管径和管长对临界热流密度的影响。不锈钢管保持在垂直方向。管的直径范围为1.2 mm ~ 9mm。管长从50mm到1000mm不等。已经注意到,对于给定的长度,直径较小的管显示出更大的CHF幅度。对于给定的直径,较长的管子比长度较小的管子具有更低的CHF。对于直径大于2.5 mm且长度超过200 mm的管,CHF大小的变化可以忽略不计。CHF发生的位置在垂直管的下端附近。研究说明了不同管径和不同热流密度下的气泡成核行为。分析了不同管道中气泡的产生和分离。根据入泡和离泡的行为对池沸腾状态进行了分类和研究。本文提出了一种计算管道尺寸(即长度和直径)对池沸腾CHF影响的数学关系。池沸腾过程中获得的实验CHF数据被制成表格,以供CHF数据库使用。
Experimental Analysis Of Bubble Behavior And Critical Heat Flux During Pool Boiling On Vertical Circular Tubes
The heat transfer during pool boiling incorporates a higher rate of heat dissipation capability at low-temperature differences. This technique is widely used in the nuclear industry for thermal management. In this study, the effect of tube diameter and length on critical heat flux (CHF) at atmospheric conditions in saturated water during pool boiling is analyzed. The tubes of SS 304 are kept in the vertical orientation. The diameter of the tubes ranges from 1.2 mm to 9 mm. The tube lengths varying from 50mm to 1000mm. It has been noted that tubes of smaller diameter show a greater magnitude of CHF for the given length. For a given diameter, a longer tube is found to have lower CHF than the ones having lesser length. The variation in the CHF magnitude is negligible for tubes with a diameter of more than 2.5 mm beyond a length of 200 mm. The location of occurrence of CHF is near the bottom end of the vertical tube. The study illustrates the behavior of bubble nucleation for various tube dimensions and heat fluxes. The inception and detachment of bubbles for different tubes are analyzed. The pool boiling regime is categorized and studied basing the behaviour of the incepted and departed bubble. A mathematical relation that empirically accounts for the effect of tube dimensions i.e. length and diameter on pool boiling CHF is proposed. The experimental CHF data obtained during pool boiling are tabulated towards contributing to the CHF databank.
期刊介绍:
The Journal of Nuclear Engineering and Radiation Science is ASME’s latest title within the energy sector. The publication is for specialists in the nuclear/power engineering areas of industry, academia, and government.