Critical Heat Flux in a Heater Rod Bundle Cooled by R-134a Fluid near the Critical Pressure

References

• Oka , Y. 2003 . “ Research and development of the supercritical-pressure light water cooled reactors ” . In Proc. 10th Int. Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-10) Seoul , , Korea Paper KL-02
   Google Scholar
• Squarer , D. , Schulenberg , T. Struwe , D. 2003 . High performance light water reactor . Nucl. Eng. Des. , 221 : 167
   Web of Science ®Google Scholar
• Jackson , J. D. and Hall , W. 1979 . Turbulent Forced Convection in Channels and Bundles, Forced convection heat transfer to fluids at supercritical pressure Edited by: Kaka , S. and Spalding , D. B. Vol. 2 , 563 Hemisphere Edited by
   Google Scholar
• Yamashita , T. , Mori , H. Yoshida , S. 2003 . Heat transfer and pressure drop of a supercritical pressure fluid flowing in a tube of small diameter . Memoirs of the Faculty of Engineering, Kyushu University , 63 ( 4 )
   Google Scholar
• Dumaz , P. and Antoni , O. 2003 . “ The extension of the CATHARE2 computer cods above the critical point, applications to a supercritical light water reactor ” . In Proc. 10th Int. Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-10) Seoul , , Korea Paper I00403
   Google Scholar
• Kaka , S. 1991 . “ Chapter 6 ” . In Boilers, Evaporators, and Condensers, , 3rd edition New York : John Wiley & Sons .
   Google Scholar
• Katto , Y. 1984 . An improved version of the generalized correlation of critical heat flux for the forced convective boiling in uniformly heated vertical tubes . Int. J. Heat Mass Transfer , 27 : 1641
   Web of Science ®Google Scholar
• Yin , S. , Lui , T. J. Huang , Y. D. 1988 . Measurements of critical heat flux in forced flow at pressures up to the vicinity of the critical point of water . Proc. 1988 National Heat Transfer Conf. , 1 : 501 U.S.A., Houston, U.S.A, July 24–27
   Google Scholar
• Groeneveld , D. C. , Leung , K. H. Kirillov , P. L. 1996 . The 1995 look-up table for critical heat flux in tubes . Nucl. Eng. Des. , 163
   Google Scholar
• Hong , S. D. , Chun , S. Y. Kim , S. Y. 2004 . Heat transfer characteristics of an internally-heated annulus cooled with R-134a near the critical pressure . J. Korean Nuclear Society , 36 ( 5 ) : 403
   Google Scholar
• Yang , S. K. , Chun , S. Y. Chung , H. J. 1995 . “Measurements of turbulent flow in 5 × 5 PWR rod bundles with spacer grids . J. Korean Nuclear Society , 24 ( 3 ) : 236
   Google Scholar
• MaLinden , M. O. , Klein , S. A. Lemmon , E. W. 2003 . REFPROP, Thermodynamic and Transport Properties of Refrigerants and Refrigerant Mixtures , NIST Standard Reference Database 23-Version 6.01 National Institute of Standards and Technology .
   Google Scholar
• ANSI/ASME PTC 19.1 . 1985 . ASME Performance Test Codes, Supplement on instruments and apparatus, part 1, measurement uncertainty , ASME, New York
   Google Scholar
• Moon , S. K. , Chun , S. Y. Cho , S. 2005 . “An experimental study on the critical heat flux for low flow of water in a non-uniformly heated vertical rod bundle over a wide range of pressure conditions . Nucl. Eng. Des. , 235 : 2295
   Google Scholar
• Chun , S. Y. , Chung , H. J. Hong , S. D. 2000 . Critical heat flux in uniformly heated vertical annulus under a wide range of pressures-0.57 to 15.0 MPa . J. Korean Nuclear Society , 32 ( 2 ) : 128
   Google Scholar
• Collier , J. G. and Thome , J. R. 1994 . Convective Boiling and Condensation, , 3rd edition 361 Oxford University Press .
   Google Scholar