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TAO Ling(陶玲), HU Chundong(胡纯栋), XIE Yuanlai(谢远来). Numerical Simulation of Subcooled Boiling Inside High-Heat-Flux Component with Swirl Tube in Neutral Beam Injection System[J]. Plasma Science and Technology, 2014, 16(5): 512-520. DOI: 10.1088/1009-0630/16/5/12
Citation: TAO Ling(陶玲), HU Chundong(胡纯栋), XIE Yuanlai(谢远来). Numerical Simulation of Subcooled Boiling Inside High-Heat-Flux Component with Swirl Tube in Neutral Beam Injection System[J]. Plasma Science and Technology, 2014, 16(5): 512-520. DOI: 10.1088/1009-0630/16/5/12

Numerical Simulation of Subcooled Boiling Inside High-Heat-Flux Component with Swirl Tube in Neutral Beam Injection System

Funds: supported by the Special Program of ITER (International Thermonuclear Experimental Reactor) in China (No. 2013GB101002)
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  • Received Date: December 13, 2012
  • In order to realize steady-state operation of the neutral beam injection (NBI) system with high beam energy, an accurate thermal analysis and a prediction about working conditions of heat-removal structures inside high-heat-flux (HHF) components in the system are key issues. In this paper, taking the HHF ion dump with swirl tubes in NBI system as an example, an accurate thermal dynamic simulation method based on computational fluid dynamics (CFD) and the finite volume method is presented to predict performance of the HHF component. In this simulation method, the Eulerian multiphase method together with some empirical corrections about the inter-phase transfer model and the wall heat flux partitioning model are considered to describe the subcooled boiling. The reliability of the proposed method is validated by an experimental example with subcooled boiling inside swirl tube. The proposed method provides an important tool for the refined thermal and flow dynamic analysis of HHF components, and can be extended to study the thermal design of other complex HHF engineering structures in a straightforward way. The simulation results also verify that the swirl tube is a promising heat removing structure for the HHF components of the NBI system.
  • 1. Tao L, Xie Y L, Hu C D, et al. 2010, Fusion Engineer- Champaign, Urbana, USA. ing and Design, 85: 2095.
    2. Pietro D E, Inoue T, Panasenkov A, et al. 2000, Fusion Engineering and Design, 49-50: 177
    3. Chen P. 2007, An experimental investigation of crit-ical heat °ux performance of hypervapotron in sub-cooled boiling [Ph.D]. University of Illinois at Urbana-Champaign, Urbana, USA
    4. Araki M, Ogawa M, Kunugi T, Kazuyoshi S, et al.1996, International Journal of Heat and Mass Trans-fer, 39: 3045
    5. Milora S L, Combs S K, Foster C A. 1986, Nuclear Engineering and Design, 3: 301
    6. Flater H D, Thompson E. 1996, Fusion Technology, 29: 584
    7. Inasaka F, Nariai H. 1998, Fusion Engineering and De-sign, 39-40: 347
    8. Narumanchi S, Troshko A, Bharathan D, et al. 2008, International Journal of Heat and Mass Transfer, 51: 1
    9. Boscary J, Fabre J, Schlosser J. 1999, International Journal of Heat and Mass Transfer, 42: 287
    10. Koncar B, Mavko B. 2003, Nuclear Engineering and Design, 220: 255
    11. Drizius M R M, Skema R K, Slanciauskas A A. 1978, Heat Transfer Soviet Research, 10: 1
    12. Marshall T D, Youchison D L, Cadwallaser L C. 2001, Fusion Technology, 39: 849
    13. Wang F J. 2004, Computation Fluid Dynamics Dy-namics: the Basic Principle and Application of CFD. Tsinghua University Press, Beijing, China (in Chinese)
    14. Milnes J, Chuilon B, Xue Y, et al. 2007, Nuclear En-gineering and Design, 82: 945
    15. Bournonville Y, Grandottoa M, Pascal-Ribot S, et al. 2009, Nuclear Engineering and Design, 84: 501
    16 Heung S, Jeong Y H, Shin B S. 2006, Nuclear Engi-neering and Technology, 38: 753
    17. Bharadwaj P, Khondge A D, Date A W. 2009, Inter-national Journal of Heat and Mass Transfer, 52: 1938
    18. Tao L, Xie Y L, Hu C D, et al. 2010, Numerical Analy-sis for the Swirl Tube Structure of the Cooling in Neutral Beam Injection System. 18th International Conference on Nuclear Engineering, Xi’an, China
    19. Lu Z Q. 2002, Two-phase Flow and Boiling Heat Transfer. Tsinghua University Press, Beijing, China (in Chinese)
    20. Podowski R M, Drew D A, Lahey R T, et al. 1997, A mechanistic model of the ebullition cycle in forced convection subcooled boiling. Proceedings of the 8th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Kyoto, Japan
    21. Valle V H D, Kenning D B R. 1985, International Jour-nal of Heat and Mass Transfer, 28: 1907
    22. Yuan D Z. 2008, Two phase .ow model and conju-gate heat transfer for heat pipe heat exchanger [Ph.D]. DaLian University of Technology, DaLian, China (in Chinese)
    23. ANSYS, Inc. 2011, ANSYS FLUENT Theory Guide. Canonsburg, http://www.ansys.com
    24. Kurul N, Podowski M Z. 1990, Multi-dimensional ef-fects in forced convection subcooled boiling. Ninth In-ternational Heat Transfer Conference, Jerusalem, Is-rael
    25. Moraga F J, Bonetot F J, Lahey R T. 1999, Interna-tional Journal of Multiphase Flow, 25: 1321
    26. Troshko A A, Hassan Y A. 2001, International Journal of Multiphase Flow, 27: 1965
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