Experimental investigation on heat transfer characteristics of water in vertical upward tube under supercritical pressure

Hedongli Gongcheng/Nuclear Power Engineering

Volumn 32, Issue 1, 2011, Pages 75-80

  Pan, Jie ^a   Yang, Dong ^a   Dong, Zi Chun ^a   Zhu, Tan ^a   Bi, Qin Cheng ^a  

^a XI'AN JIAOTONG UNIVERSITY   (China)

Author keywords

Heat transfer coefficient; Heat transfer enhancement; Pseudo critical temperature; Smooth tube; Supercritical pressure; Wall temperature

Indexed keywords

HEAT TRANSFER ENHANCEMENT; PSEUDO-CRITICAL TEMPERATURE; SMOOTH TUBES; SUPERCRITICAL PRESSURES; WALL TEMPERATURE;

ENTHALPY; EXPERIMENTS; FLUIDS; HEAT TRANSFER COEFFICIENTS; TEMPERATURE; TUBES (COMPONENTS);

HEAT FLUX;

EID: 79953204651     PISSN: 02580926     EISSN: None     Source Type: Journal    
DOI: None     Document Type: Article

References (16)

1. Oka Y, Koshizuka S. Design Concept of Once-Through Cycle Supercritical Pressure Light Water Cooled Reactors[C]. Proc of SCR-2000, Tokyo, Japan, 1-22.
2. Yoo J, Ishiwatari Y, Oka Y, et al. Composite Core Design of High Power Density Supercritical Water Cooled Fast Reactor[C]. Proc Of GLOBAL2005, Tsukuba, Japan: 246-251.
3. Kamei K, Yamaji A, Ishiwatari Y, et al. Fuel and Core Design of Super Light Water Reactor with Low Leakage Fuel Loading Pattern[J]. J Nucl Sci Technol, 2006, 43(2): 129-19.
4. Oka Y, Ishiwatari Y, Koshizuka S. Research and Development of Super LWR and Super Fast Reactor[C]. Proc of SCWR, Shanghai, China, 2007: 9-8.
5. Song J H, Kim H Y, Kim H, et al. Heat Transfer Characteristics of a Supercritical Fluid Flow in a Vertical Pipe[J]. Journal of Supercritical Fluids, 2008, 44: 164-171.
6. Liao S M, Zhao T S. An Experimental Investigation of Convection Heat Transfer to Supercritical Carbon Dioxide in Miniature Tubes[J]. Int J Heat Mass Transfer, 2002, 45: 5025-5034.
7. 2 at Supercritical Pressures in Vertical Mini Tubes and in Porous Media[J]. Applied Thermal Engineering, 24 (2004) 1255-1270.
8. 2 in a Horizontal Circular Tube[J]. Journal of Supercritical Fluids 2007, 41: 412-420.
9. 2 at Supercritical Pressures[J]. Journal of Nuclear Science and Technology, 2007, 44(3): 285-293.
10. Igor L P, Hussam F K, Romney B D. Heat Transfer to Supercritical Fluids Flowing in Channels-Empirical Correlations(survey)[J]. Nuclear Engineering and Design, 2004, 230: 69-91.
11. 2001, 35(1): 10-14.
12. 2001, 16(93): 267-270.
13. Zhu Xiaojing, Bi Qincheng, Yang Dong, et al. An Investigation on Heat Transfer Characteristics of Different Pressure Steam-Water in Vertical Upward Tube[J]. Nuclear Engineering and Design, 2009, 239: 381-388.
14. Cheng L, Chen T. Flow boiling Heat Transfer in a Vertical Spirally Internally Ribbed Tube[J]. Heat and Mass Transfer, 2001(37): 229-236.
15. Ackerman J W. Pseudo-Boiling Heat Transfer to Supercritical Pressure Water in Smooth and Ribbed Tubes[J]. Journal of Heat transfer, 1970, pp. 490-498.
16. 1998.