851
Views
10
CrossRef citations to date
0
Altmetric
ARTICLE

Numerical Simulation of Fluid Flow and Heat Transfer of Supercritical Fluids in Fuel Bundles

, &
Pages 929-935 | Received 23 Sep 2010, Accepted 17 Jan 2011, Published online: 05 Jan 2012

References

  • US NERAC and GIF . 2002 . A Technology Roadmap for Generation IV Nuclear Energy Systems, The U.S. DOE Nuclear Energy Research Advisory Committee and the Generation IV International Forum
  • Cheng , X. and Tak , N. I. 2006 . “CFD analysis of thermal-hydraulic behaviour of heavy liquid metals in sub-channels” . Nucl. Eng. Des. , 236 : 1874 – 1885 .
  • Chang , D. and Tavoularis , S. 2005 . “Unsteady numerical simulations of turbulence and coherent structures in axial flow near a narrow gap” . ASME J. Fluids Eng. , 127 ( 3 ) : 458 – 466 .
  • Chang , D. and Tavoularis , S. 2008 . “Simulations of turbulence, heat transfer and mixing across narrow gaps between rod-bundle subchannels” . Nucl. Eng. Des. , 238 : 109 – 123 .
  • Chang , D. and Tavoularis , S. 2007 . “Numerical simulation of turbulent flow in a 37-rod bundle” . Nucl. Eng. Des. , 237 : 575 – 590 .
  • Cheng , X. , Laurien , E. and Yang , Y. H. 2005 . “CFD analysis of heat transfer in supercritical water in different flow channels” . In Proc. Int. Conf. Nuclear Energy Systems for Future Generation and Global Sustainability (GLOBAL 2005) 369 Tsukuba , , Japan Oct. 9–13, 2005, Paper No
  • Cheng , X. , Kuang , B. and Yang , Y. H. 2007 . “Numerical analysis of heat transfer in supercritical water cooled flow channels” . Nucl. Eng. Des. , 237 : 240 – 252 .
  • Yang , J. , Oka , Y. , Ishiwatari , Y. , Liu , J. and Yoo , J. 2007 . “Numerical investigation of heat transfer in upward flows of supercritical water in circular tubes and tight fuel rod bundles” . Nucl. Eng. Des. , 237 : 420 – 430 .
  • Gu , H. Y. , Cheng , X. and Yang , Y. H. 2008 . “CFD analysis of thermalhydraulic behavior of supercritical water in sub-channels” . Nucl. Eng. Des. , 238 : 3348 – 3359 .
  • Torgerson , D. F. , Shalaby , B. A. and Pang , S. 2006 . “CANDU technology for Generation III+ and IV reactors” . Nucl. Eng. Des. , 236 : 1565 – 1572 .
  • Dimmick , G. R. , Chatoorgoon , V. , Khartabil , H. F. and Duffey , R. B. 2002 . “Natural-convection studies for advanced CANDU reactor concepts” . Nucl. Eng. Des. , 215 : 27 – 38 .
  • Cheng , X. , Schulenberg , T. , Bittermann , D. and Rau , P. 2003 . “Design analysis of core assemblies for supercritical pressure conditions” . Nucl. Eng. Des. , 223 : 279 – 294 .
  • Yu , J. , Wang , S. and Jia , B. 2007 . “Development of sub-channel analysis code for CANDU-SCWR” . Prog. Nucl. Energy , 49 : 334 – 350 .
  • Li , C. 2008 . Subchannel Analysis of Supercritical Water Reactor Master Thesis, Xi'an Jiaotong University, China
  • Zhang , Y. N. , Zhang , C. and Jiang , J. 2010 . “Numerical simulation of heat transfer of supercritical fluids in circular tubes using different turbulence models,” submitted to . J. Nucl. Sci. Technol. ,
  • 2002 . Heavy Water Reactors: Status and Projected Development , Technical Report Series No. 407 International Atomic Energy Agency .
  • Duffey , R. , Pioro , I. and Khartabil , H. 2005 . “Supercritical water-cooled pressure channel nuclear reactors: Review and status” . In Proc. Int. Conf. Nuclear Energy Systems for Future Generation and Global Sustainability (GLOBAL 2005) 020 Tsukuba , , Japan Oct. 9–13, 2005, Paper No
  • Bushby , S. J. , Dimmick , G. R. , Duffey , R. B. , Burrill , K. A. and Chan , R. S. W. 2000 . “Conceptual designs for advanced, high-temperature CANDU reactors” . In Proc. 8th Int. Conf. on Nuclear Engineering Baltimore , , USA Apr. 2–6, 2000, ICONE-8470
  • Duffey , R. B. , Shalaby , B. A. , Torgerson , D. F. , Khartabil , H. F. and Hopwood , J. M. 2004 . “CANDU and Generation IV system,” 14th ” . In Pacific Basin Nuclear Conf. on ‘New Technologies for a New Era,’ Honolulu, Hawaii , , USA Mar. 21–25, 2004
  • Khartabil , H. F. , Duffey , R. B. , Spinks , N. and Diamond , W. 2005 . “The pressure-tube concept of Generation IV supercritical watercooled reactor (SCWR): Overview and status” . In Int. Congress on Advances in Nuclear Power Plants Seoul , , Korea May 15–19, 2005
  • Torgerson , D. F. , Shalaby , B. A. and Pang , S. 2006 . “CANDU technology for Generation III+ and IV reactors” . Nucl. Eng. Des. , 236 : 1565 – 1572 .
  • Wagner , W. and Kruse , A. 1998 . Properties of Water and Steam: The Industrial Standard IAPWS-IF 97 for the Thermodynamic Properties and Supplementary Equations for Other Properties New York : Springer .
  • 2006 . Fluent 6.3 User's Guide
  • Tao , W. Q. 2003 . Numerical Heat Transfer (Second Edition) Xi'an : Xi'an Jiaotong University Press .
  • Wolfstein , M. 1969 . “The velocity and temperature distribution of one-dimensional flow with turbulence augmentation and pressure gradient” . Int. J. Heat Mass Transfer , 12 : 301 – 318 .

Reprints and Corporate Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

To request a reprint or corporate permissions for this article, please click on the relevant link below:

Academic Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

Obtain permissions instantly via Rightslink by clicking on the button below:

If you are unable to obtain permissions via Rightslink, please complete and submit this Permissions form. For more information, please visit our Permissions help page.