Deepak K. Solanki , Kausik Nandi , Joe Mohan , Arunkumar Sridharan , S.V. Prabhu
{"title":"Subcooled flow boiling in a horizontal circular pipe under high heat flux and high mass flux conditions","authors":"Deepak K. Solanki , Kausik Nandi , Joe Mohan , Arunkumar Sridharan , S.V. Prabhu","doi":"10.1016/j.anucene.2024.111030","DOIUrl":null,"url":null,"abstract":"<div><div>Subcooled flow boiling of water is widely observed in high heat flux and high mass flux (HHHM) cooling applications such as heat exchangers, refrigeration equipment, boiler tubes and nuclear reactor core fuel channels in pressurized heavy water reactors (PHWR). In this study, the focus is on investigating the local heat transfer coefficient (HTC) and pressure drop in a horizontal tube experiencing subcooled boiling of water under low pressure and HHHM conditions. The study encompasses different geometrical parameters such as tube diameter (5.5 <em>mm</em>, 7.5 <em>mm</em>, 9.5 <em>mm</em> and 12 <em>mm</em>) and length (550 <em>mm</em> for each of the tubes). The operating parameters that are varied include mass flux (248–2000 <em>kg/m</em><sup><em>2</em></sup><sup><em>.</em></sup><em>s</em>) and heat flux (0–1837 <em>kW/m</em><sup><em>2</em></sup>). Infrared thermography is used to measure the local wall temperature. A non-dimensional correlation for the diabatic pressure drop ratio (ratio of diabatic pressure drop to adiabatic pressure drop) as a function of Jakob number (<span><math><mrow><mi>Ja</mi></mrow></math></span>), Boiling number (<span><math><mrow><mi>Bo</mi></mrow></math></span>) and diameter ratio is developed. Subcooled boiling pressure drop ratio for 5.5 <em>mm</em>, 7.5 <em>mm</em> and 9.4 <em>mm</em> diameter tubes is 2.23 which is independent of diameter. A correlation for the two phase local HTC during subcooled flow boiling conditions as a function of <span><math><mrow><mi>Ja</mi></mrow></math></span>, <span><math><mrow><mi>Bo</mi></mrow></math></span> and Prandtl number (<span><math><mrow><mi>Pr</mi></mrow></math></span>) is also developed.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"212 ","pages":"Article 111030"},"PeriodicalIF":1.9000,"publicationDate":"2024-11-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Annals of Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0306454924006935","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0
Abstract
Subcooled flow boiling of water is widely observed in high heat flux and high mass flux (HHHM) cooling applications such as heat exchangers, refrigeration equipment, boiler tubes and nuclear reactor core fuel channels in pressurized heavy water reactors (PHWR). In this study, the focus is on investigating the local heat transfer coefficient (HTC) and pressure drop in a horizontal tube experiencing subcooled boiling of water under low pressure and HHHM conditions. The study encompasses different geometrical parameters such as tube diameter (5.5 mm, 7.5 mm, 9.5 mm and 12 mm) and length (550 mm for each of the tubes). The operating parameters that are varied include mass flux (248–2000 kg/m2.s) and heat flux (0–1837 kW/m2). Infrared thermography is used to measure the local wall temperature. A non-dimensional correlation for the diabatic pressure drop ratio (ratio of diabatic pressure drop to adiabatic pressure drop) as a function of Jakob number (), Boiling number () and diameter ratio is developed. Subcooled boiling pressure drop ratio for 5.5 mm, 7.5 mm and 9.4 mm diameter tubes is 2.23 which is independent of diameter. A correlation for the two phase local HTC during subcooled flow boiling conditions as a function of , and Prandtl number () is also developed.
期刊介绍:
Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.