External reactor vessel cooling (ERVC) is the key technology for In-Vessel Retention (IVR) to ensure the safety of a nuclear power plant (NPP) under severe accident conditions. The thermal margin of nucleate boiling heat transfer on the reactor pressure vessel (RPV) lower head is important for ERVC and of wide concern to researchers. In such boiling heat transfer processes, the reactor vessel wall inclination effect on the heat transfer coefficient (HTC) and critical heat flux (CHF) should be considered. In this study, experiments were performed to investigate the effects of heater material and surface orientation on the HTC and CHF of nucleate boiling. Copper and stainless steel (SS) surfaces were used to perform boiling tests under atmosphere pressure. The orientation angle of both boiling surfaces were varied between 0° (upward) and 180° (downward). The experimental results show that the surface orientation effects on the HTC is slight for both the copper surface and the SS surface. In addition, the relationship of measured CHF values with the inclination angles was obtained and it shows that the CHF value changes little as the inclination angle increases from 0° to 120° but it decreases rapidly as the orientation angle increases towards 180° for both boiling surfaces. The material effect on CHF is also observed and the copper surface has higher CHF value than the SS surface. Based on the experimental data, a correlation for CHF prediction is developed which includes both the surface orientation effect and the heater material effect.
Skip Nav Destination
2017 25th International Conference on Nuclear Engineering
July 2–6, 2017
Shanghai, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5784-7
PROCEEDINGS PAPER
Effects of Heater Material and Surface Orientation on Heat Transfer Coefficient and Critical Heat Flux of Nucleate Boiling Available to Purchase
Yong Mei,
Yong Mei
Shanghai Jiao Tong University, Shanghai, China
Search for other works by this author on:
Yechen Zhu,
Yechen Zhu
Shanghai Jiao Tong University, Shanghai, China
Search for other works by this author on:
Botao Zhang,
Botao Zhang
Shanghai Jiao Tong University, Shanghai, China
Search for other works by this author on:
Shengjie Gong,
Shengjie Gong
Shanghai Jiao Tong University, Shanghai, China
Search for other works by this author on:
Hanyang Gu
Hanyang Gu
Shanghai Jiao Tong University, Shanghai, China
Search for other works by this author on:
Yong Mei
Shanghai Jiao Tong University, Shanghai, China
Yechen Zhu
Shanghai Jiao Tong University, Shanghai, China
Botao Zhang
Shanghai Jiao Tong University, Shanghai, China
Shengjie Gong
Shanghai Jiao Tong University, Shanghai, China
Hanyang Gu
Shanghai Jiao Tong University, Shanghai, China
Paper No:
ICONE25-67142, V006T08A083; 8 pages
Published Online:
October 17, 2017
Citation
Mei, Y, Zhu, Y, Zhang, B, Gong, S, & Gu, H. "Effects of Heater Material and Surface Orientation on Heat Transfer Coefficient and Critical Heat Flux of Nucleate Boiling." Proceedings of the 2017 25th International Conference on Nuclear Engineering. Volume 6: Thermal-Hydraulics. Shanghai, China. July 2–6, 2017. V006T08A083. ASME. https://doi.org/10.1115/ICONE25-67142
Download citation file:
49
Views
Related Proceedings Papers
Related Articles
Microelectronic Cooling by Enhanced Pool Boiling of a Dielectric Fluorocarbon Liquid
J. Heat Transfer (August,1989)
Nucleate Boiling Heat Transfer on Plain and Microporous Surfaces in Subcooled Water
J. Heat Transfer (August,2017)
Confined Jet Impingement With Boiling on a Variety of Enhanced Surfaces
J. Heat Transfer (October,2014)
Related Chapters
Development of Nuclear Boiler and Pressure Vessels in Taiwan
Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 3, Third Edition
Source Term Assessments in PSA Level 2 for the Outage Period (PSAM-0168)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
PSA Level 2 — NPP Ringhals 2 (PSAM-0156)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)