{"title":"垂直螺旋盘管中水饱和沸腾的实验研究","authors":"Yuqing Su, Xiaowei Li, Xinxin Wu","doi":"10.1016/j.anucene.2025.111464","DOIUrl":null,"url":null,"abstract":"<div><div>Helically coiled tubes are used in the High Temperature Gas-cooled Reactor (HTGR) Once Through Steam Generator (OTSG). However, due to centrifugal forces and secondary flows, heat transfer characteristics inside these tubes may differ from that in straight tubes. A clear understanding of the heat transfer inside helically coiled tubes is essential for the design and operation of the OTSG. In this study, we experimentally investigated saturated flow boiling in helically coiled tubes with a large curvature ratio (<em>δ</em> = 0.109). The experimental parameters cover a broad range. The system pressure is from 3.5 to 7 MPa, mass flux is from 300 to 1100 kg/(m<sup>2</sup>·s) and heat flux is from 50 to 600 kW/m<sup>2</sup>. Results show that the inner wall temperature distribution is uneven, with the highest temperature on the inner side and the lowest on the outer side. Increasing heat flux enhances the saturated flow boiling heat transfer coefficient. At low steam quality, the heat transfer coefficient is not significantly affected by mass flux variations. However, at higher steam quality, increasing mass flux improves heat transfer. An increase in system pressure enhances the heat transfer coefficient at lower steam qualities but reduces it at higher steam qualities. Six correlations for the saturated flow boiling were evaluated, with the Gungor-Winterton correlation originally developed for straight tubes showing accurate predictions for heat transfer coefficients in helically coiled tubes (MAPE is 12.72 %, RMS is15.36 %). This indicates that even in helically coiled tubes with a large curvature ratio, no significant difference is observed in the saturated flow boiling heat transfer coefficient compared to straight tubes.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"219 ","pages":"Article 111464"},"PeriodicalIF":1.9000,"publicationDate":"2025-04-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Experimental investigation of saturated flow boiling of water in vertical helically coiled tubes\",\"authors\":\"Yuqing Su, Xiaowei Li, Xinxin Wu\",\"doi\":\"10.1016/j.anucene.2025.111464\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>Helically coiled tubes are used in the High Temperature Gas-cooled Reactor (HTGR) Once Through Steam Generator (OTSG). However, due to centrifugal forces and secondary flows, heat transfer characteristics inside these tubes may differ from that in straight tubes. A clear understanding of the heat transfer inside helically coiled tubes is essential for the design and operation of the OTSG. In this study, we experimentally investigated saturated flow boiling in helically coiled tubes with a large curvature ratio (<em>δ</em> = 0.109). The experimental parameters cover a broad range. The system pressure is from 3.5 to 7 MPa, mass flux is from 300 to 1100 kg/(m<sup>2</sup>·s) and heat flux is from 50 to 600 kW/m<sup>2</sup>. Results show that the inner wall temperature distribution is uneven, with the highest temperature on the inner side and the lowest on the outer side. Increasing heat flux enhances the saturated flow boiling heat transfer coefficient. At low steam quality, the heat transfer coefficient is not significantly affected by mass flux variations. However, at higher steam quality, increasing mass flux improves heat transfer. An increase in system pressure enhances the heat transfer coefficient at lower steam qualities but reduces it at higher steam qualities. Six correlations for the saturated flow boiling were evaluated, with the Gungor-Winterton correlation originally developed for straight tubes showing accurate predictions for heat transfer coefficients in helically coiled tubes (MAPE is 12.72 %, RMS is15.36 %). This indicates that even in helically coiled tubes with a large curvature ratio, no significant difference is observed in the saturated flow boiling heat transfer coefficient compared to straight tubes.</div></div>\",\"PeriodicalId\":8006,\"journal\":{\"name\":\"Annals of Nuclear Energy\",\"volume\":\"219 \",\"pages\":\"Article 111464\"},\"PeriodicalIF\":1.9000,\"publicationDate\":\"2025-04-14\",\"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/S0306454925002816\",\"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}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Annals of Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0306454925002816","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}
Experimental investigation of saturated flow boiling of water in vertical helically coiled tubes
Helically coiled tubes are used in the High Temperature Gas-cooled Reactor (HTGR) Once Through Steam Generator (OTSG). However, due to centrifugal forces and secondary flows, heat transfer characteristics inside these tubes may differ from that in straight tubes. A clear understanding of the heat transfer inside helically coiled tubes is essential for the design and operation of the OTSG. In this study, we experimentally investigated saturated flow boiling in helically coiled tubes with a large curvature ratio (δ = 0.109). The experimental parameters cover a broad range. The system pressure is from 3.5 to 7 MPa, mass flux is from 300 to 1100 kg/(m2·s) and heat flux is from 50 to 600 kW/m2. Results show that the inner wall temperature distribution is uneven, with the highest temperature on the inner side and the lowest on the outer side. Increasing heat flux enhances the saturated flow boiling heat transfer coefficient. At low steam quality, the heat transfer coefficient is not significantly affected by mass flux variations. However, at higher steam quality, increasing mass flux improves heat transfer. An increase in system pressure enhances the heat transfer coefficient at lower steam qualities but reduces it at higher steam qualities. Six correlations for the saturated flow boiling were evaluated, with the Gungor-Winterton correlation originally developed for straight tubes showing accurate predictions for heat transfer coefficients in helically coiled tubes (MAPE is 12.72 %, RMS is15.36 %). This indicates that even in helically coiled tubes with a large curvature ratio, no significant difference is observed in the saturated flow boiling heat transfer coefficient compared to straight tubes.
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.