Numerical analysis of thermal-hydraulic behavior of supercritical water in vertical upward/downward flow channels

Hanyang GU; Yiqi YU; Xu CHENG; Xiaojing LIU

doi:10.1016/S1001-8042(08)60047-0

Your Location：

Home >

Browse articles >

Numerical analysis of thermal-hydraulic behavior of supercritical water in vertical upward/downward flow channels

MISCELLANEOUS | Updated：2021-01-29

- Numerical analysis of thermal-hydraulic behavior of supercritical water in vertical upward/downward flow channels
- Nuclear Science and Techniques Vol. 19, Issue 3, (2008)
- Affiliations：
  
  1.School of Nuclear Science and Engineering, Shanghai Jiaotong University, Shanghai 200240, China
- Author bio：
  
  Corresponding author. E-mail: guhanyang@stju.edu.cn
- Funds：
- DOI：10.1016/S1001-8042(08)60047-0
  CLC：
Scan for full text
Cite this article
Hanyang GU, Yiqi YU, Xu CHENG, et al. Numerical analysis of thermal-hydraulic behavior of supercritical water in vertical upward/downward flow channels. [J]. Nuclear Science and Techniques 19(3):178-186(2008)
DOI：

Hanyang GU, Yiqi YU, Xu CHENG, et al. Numerical analysis of thermal-hydraulic behavior of supercritical water in vertical upward/downward flow channels. [J]. Nuclear Science and Techniques 19(3):178-186(2008) DOI： 10.1016/S1001-8042(08)60047-0.

摘要

Abstract

Investigations on the thermal-hydraulic behavior in the SCWR fuel assembly have obtained a significant attention in the international SCWR community. However, there is still a lack of understanding of the heat transfer behavior of supercritical fluids. In this paper, the numerical analysis is carried out to study the thermal-hydraulic behaviour in vertical sub-channels cooled by supercritical water. Remarkable differences in characteristics of secondary flow are found, especially in square lattice, between the upward flow and downward flow. The turbulence mixing across sub-channel gap for downward flow is much stronger than that for upward flow in wide lattice when the bulk temperature is lower than pseudo-critical point temperature. For downward flow, heat transfer deterioration phenomenon is suppressed with respect to the case of upward flow at the same conditions.

关键词

Keywords

Supercritical water reactorCFDHeat transfer

references

Oka Y, Koshizuka S, Design concept of once-through cycle supercritical pressure light water cooled reactors. In: Proceeding of SCR. Tokyo, Japan, November 6-8, 2000, 1-22.

Yoo J, Ishiwatari Y, Oka Y, et al. Composite core design of high power density supercritical water cooled fast reactor. (Paper No.246) In: Proceeding of GLOBAL2005, Tsukuba, Japan, October 9-13,2005.

Kamei K, Yamaji A, Ishiwatari Y, et al. J Nucl Sci Technol, 2006, 43:129-139.

Schulenberg T, Starflinger J, European research project on high performance light water reactors. In: Proceeding of SCWR-2007, Shanghai, China, March 12-15, 2007, 1-8.

Oka Y, Ishiwatari Y, Koshizuka S, Research and development of super LWR and super fast reactor. In: Proceeding of SCWR-2007, Shanghai, China, March.12-15, 2007, 9-18.

Jackson JD, Hall WB. Forced convection heat transfer to fluids at supercritical pressure. In: Kakaç S, Spalding D B (Eds.), Turbulent forced convection in channels and bundles, vol. 2. New York: Hemisphere Publishing Corp. 1979:563-612.

Polyakov A F,Adv. Heat Transfer, 1991, 21:1-51.

Cheng X, Schulenberg T, Heat transfer at supercitical pressure-literature review and application to a HPLWR. Scientific Report FZKA6609.2001

Pioro I L, Khartabil H F, Duffey R.B. Nucl Eng Des,2004, 230: 69-91.

Pioro I L, Duffey RB. Nucl Eng Des, 2005, 235:2407-2430.

Silin V A, Voznesensky V A, Afrov A M. Nucl. Eng. Des,1993,144:327-336.

Shiralkar B S, Griffith P J. Heat Transfer,1969, 3: 27-36

Kim S H, Kim Y I, Bae YY, et al. Numerical simulation of the vertical upward flow of water in a heated tube at supercritical pressure. Proc. ICAP,2004.

Roelof F, Komen Ed, CFD analysis of heat transfer to supercritical water flowing vertically upward in a tube, Jahrestagung Kerntechnik, Germany, 2005.

Yang J, Oka Y, Ishiwatari Y, et al. Nucl Eng Des.2007, 237:420-430.

Hassid S, Poreh M, J Fluids Eng, 1978, 100: 107-112.

Kjellström B, Studies of turbulent flow parallel to a rod bundle of triangular array. Report AE-RV-196, AB Atomenergi, Sweden,1971

Trupp A C, Azad R S. Nucl Eng Des, 1975, 32: 47-84.

Vonka V. Nucl Eng Des, 1988, 106:191-207.

Rehme K. Int J. Heat Mass Trans,1992,18: 1055-1069.

Cheng X, Kuang B, Yang Y H. Nucl Eng Des, 2007, 237:240-252.

Wagner W, Kruse A. Properties of water and steam: The industrial standard IAPWS-IF97 for the thermodynamic properties and supplementary equations for other properties, Tables based on these equation, Berlin: Springer-Verlag, 1998.

Carajilescov P, Todreas N E. J Heat Transfer, 1976. 4:262-268.

Cheng X, Tak N I. Nucl Eng Des. 2006, 236: 1874-1885.

Lin C C, Statistical theory of turbulence. Princeton: Princeton University Press, 1961.

Stewart C W, COBRA-IV: The models and the methods. Battelle Pacific Northwest Laboratories, Report BNWL-2214, 1977.

Rogers J T, Todreas N E, Coolant inter-channel mixing in reactor fuel rod bundles single-phase coolant, in section heat transfer in rod bundle. In: The winter annual meeting of ASME, New York, 1968, 1-56.

Cheng X, Muller U. Int J Multiphase Flow, 1998, 24:1245-1263.

Prandtl L, Führer durch die Strömungslehre, 3rd ed. Braunschweig: Vieweg, 1942.

Views

Downloads

CSCD

Alert me when the article has been cited

Submit

Tools

Publicity Resources

Simulation of heat transfer of supercritical water in obstacle-bearing vertical tube

Transient analysis and optimization of passive residual-heat removal heat exchanger in advanced nuclear power plant

Moving particle semi-implicit simulation on the molten Wood’s metal downward relocation process

CFD studies on the separation performance of a new combined gas-solid separator used in TMSR-SF

Study of heat transfer by using DEM-CFD method in a randomly packed pebble bed reactor

Related Author

No data

Related Institution

Schoocl of Nuclear Science and Technology, Xi'an Jiaotong University

Shanghai Nuclear Engineering Research & Design Institute, State Power Investment Corporation

Key Laboratory of Pressure Systems and Safety, Ministry of Education, East China University of Science & Technology

Nuclear Physics and Biophysics Research Division, Physics Department, Faculty of Mathematics and Natural Science, Institut Teknologi Bandung, Jalan Ganesha 10

Physics Department, Faculty of Mathematics and Natural Science, Institut Teknologi Bandung, Jalan Ganesha 10

Address：Editorial Office of NST, 2019 Jialuo Road, Jiading, Shanghai 201800, China Postal code：201800
Email：nst@sinap.ac.cn
Technical support is provided by Beijing Founder electronics co., LTD 沪ICP备05005479号-1 京公网安备11010802024621
It is recommended to read the content of this site in Chrome&IE9+. Please switch to extreme mode in browser 360.
Cookies We use cookies to help provide and enhance our service and tailor content. By continuing, you agree to the use of cookies.

⁰