Development of a Wide-Range Pre-CHF Convective Boiling Correlation

References

• Chen , J. C. 1963 . A Correlation for Boiling Heat Transfer to Saturated Fluids in Convective Flow , ASME 63-HT-34 American Society of Mechanical Engineers .
   Google Scholar
• Thom , J. R. S. , Walker , W. M. , Fallon , T. A. and Reising , G. F. S. 1966 . “Boiling in sub-cooled water during flow up heated tubes or annuli” . Proc. Inst. Mech. Engineers , 180 ( 3C ) : 226
   Google Scholar
• Jens , W. H. and Lottes , P. A. 1951 . Analysis of Heat Transfer, Burnout, Pressure Drop and Density Data for High Pressure Water , ANL-4627 Argonne National Laboratory .
   Google Scholar
• Schrock , V. E. and Grossman , L. M. 1959 . Forced Convection Boiling Studies: Final Report on Forced Convection Vaporization Project , TID-14632 Lawrence Radiation Laboratory .
   Google Scholar
• Eisenhart , L. D. , Dias , A. F. , Westacott , J. L. , Downar , T. J. and Joo , H. G. 1999 . CORETRAN-01 Volume 2: User's Manual , EPRI WO-3574 Electric Power Research Institute .
   Google Scholar
• Stewart , C. W. , Cuta , J. M. , Montgomery , S. D. , Kelly , J. M. , Basehore , K. L. , George , T. L. and Rowe , D. S. 1989 . VIPRE-01: A Thermal-Hydraulic Code for Reactor Cores—Volume 1: Mathematical Modelling (Revision 3) , EPRI NP-2511-CCMA, Electric Power Research Institute
   Google Scholar
• Kelly , J. M. , Stewart , K. C. and Cuta , J. M. 1992 . “VIPRE-02: A twofluid thermal-hydraulic code for reactor core and vessel analysis: Mathematical modelling and solution methods” . Nucl. Technol. , 100 : 246
   Web of Science ®Google Scholar
• Ransom , V. H. 1987 . RELAP5/MOD2 Code Manual Volume1: Code Structure, Systems Models, and Solution Methods , NUREG/CR-4312 (EGG-2396), Rev. 1 US Nuclear Regulatory Commission .
   Google Scholar
• Spore , J. W. , Elson , J. S. , Jolly-Woodruff , S. J. , Knight , T. D. , Lin , J. C. , Nelson , R. A. , Pasamehmetoglu , K. O. , Stein , R. G. , Unal , C. , Mahaffy , J. H. and Murray , C. 2000 . TRAC-M/Fortran 90 (Version 3.0) Theory Manual , LA-UR-00–910 Los Alamos .
   Google Scholar
• Kris?tof , M. and Vojtek , I. 2003 . “Uncertainty analyses for LB LOCA in VVER-440/213” . In Proc. EUROSAFE Forum 45 Paris , , France Nov. 25–26, 2003
   Google Scholar
• Kris?tof , M. 2004 . “Application of BE+U methodology for the licensing purposes in Slovakia” . In Proc. Int. Mtg. on Updates in Best Estimate Methods in Nuclear Installation Safety Analysis Washington, D.C. , , USA Nov. 14–18, 2004,124
   Google Scholar
• Putney , J. M. and Preece , R. J. 1993 . “ US NRC Committee ” . In Assessment of PWR Steam Generator Modelling in RELAP5/MOD2 , International Agreement Report, NUREG/IA-0106 US Nuclear Regulatory Commission .
   Google Scholar
• Boucher , T. J. 1986 . Steady-State Heat Transfer in an Inverted U-tube Steam Generator , EGG-M-07086 EG&G .
   Google Scholar
• Preece , R. J. and Putney , J. M. 1993 . “ US NRC Committee ” . In Preliminary Assessment of PWR Steam Generator Modelling in RELAP5/MOD3 , International Agreement Report, NUREG/IA-0113 US Nuclear Regulatory Commission .
   Google Scholar
• 1991 . Simulation of a Loss of Coolant Accident with a Rupture in the Steam Generator Hot Collector , Results of the Third Standard Problem Exercise, IAEA-TECDOC-586 International Atomic Energy Agency . IAEA Committee
   Google Scholar
• Boucher , T. J. 1987 . Scale Model Test Results for a U-Tube Steam Generator with Comparisons of Heat Transfer Correlations , EGG-M-36787 EG&G .
   Google Scholar
• Morgan , C. D. and Hassan , Y. A. 1986 . “On the use of the Chen boiling heat transfer correlation in once-through steam generator analysis” . Trans. Am. Nucl. Soc. , 53 : 332
   Google Scholar
• Hassan , Y. A. and Salim , P. 1990 . “Analysis of a nuclear power plant using RELAP5/MOD2 with modified bundle heat transfer correlations” . Nucl. Technol , 92 : 141
   Web of Science ®Google Scholar
• Aounallah , Y. 2008 . “A separate-effect-based new appraisal of convective boiling and its suppression” . J. Nucl. Sci. Technol , 45 ( 2 ) : 149
   Web of Science ®Google Scholar
• Macian , R. , Mahaffy , J. H. , Robinson , G. E. , Bajorek , S. M. , Hochreiter , L. E. and Smith , L. C. 1993 . “Modeling of the LOCA and post-LOCA steam generator heat release with WCOBRATRAC” . In Steam Generator Thermal Hydraulics , ASME Publication, HTD-251 19
   Google Scholar
• Escrivá , A. and March-Leuba , J. 2000 . “ LAPUR5.2 ” . In Verification and User's Manual , NUREG/CR-2000/340 US Nuclear Regulatory Commission .
   Google Scholar
• Bertoletti , S. and Lombardi , C. 1963 . Heat Transfer of Steam-Water Mixture at 70 kg/cm² in Round Tubes , Report No 97 Centro Informazioni Studi Esperienze (CISE) .
   Google Scholar
• Bertoletti , S. , Lombardi , C. and Silvestre , M. 1964 . Heat Transfer to Steam-Water Mixtures , Report R-78 Centro Informazioni Studi Esperienze (CISE) .
   Google Scholar
• Collier , J. G. and Thome , J. R. 1996 . Convective Boiling and Condensation 264 Oxford , , UK : Clarendon Press . 3rd Edition
   Google Scholar
• Dittus , F. W. and Boelter , L. M. K. 1930 . “Heat transfer in automobile radiators of a tubular type” . Engineering , 2 ( 13 ) : 443
   Google Scholar
• Borishansky , R. W. , Novikov , I. and Kutateladze , S. S. 1961 . “Use of thermodynamic similarity in generalizing experimental data of heat transfer” . In Proc. Second Int. Heat Transfer Conf. 56 Boulder , , USA Ang. 28–Sep. 1, Paper, 1961
   Google Scholar
• Dengler , C. E. and Addoms , J. N. 1956 . “Heat transfer mechanism for vaporization of water in a vertical tube” . Chemical Engineering Progress Symposium Series , 52 : 95
   Google Scholar
• Chen , J. C. and Tuzla , K. 1995 . “Contribution of convection and boiling to convective flow boiling” . In Proc. Convective Flow Boiling, Int. Conf. 181 – 186 . Alberta , , Canada Apr. 3–May 5, 1995
   Google Scholar
• Collier , J. G. and Pulling , D. J. 1962 . Heat Transfer to Two-Phase Gas-Liquid Systems United Kingdom Atomic Energy Authority . Report AERE-R3809
   Google Scholar
• Bergles , A. E. and Rohsenow , W. M. 1964 . “The determination of forced-convection surface-boiling heat transfer” . J. Heat Transfer , 86 : 365
   Google Scholar
• Bennet , J. A. R. , Collier , J. G. , Pratt , H. R. C. and Thornton , J. D. 1959 . Heat Transfer to Two-Phase Gas-Liquid Systems—Part 1: Steam-Water Mixtures in the Liquid-Dispersed Region in an Annulus , Report AERE-R3159 Atomic Energy Research Establishment (AERE) - Harwell .
   Google Scholar
• McAdams , W. M. , Kennel , W. E. , Minden , C. S. , Carl , R. , Picornell , P. M. and Dew , J. E. 1954 . “Heat transfer at high rates to water with surface boiling” . Ind. Eng. Chem , 41 ( 9 ) : 1945
   Google Scholar
• Sekoguchi , K. , Nishikawa , K. , Nakasatomi , M. , Hirata , N. and Higuchi , H. 1974 . “Flow boiling in subcooled and low quality regions— Heat transfer and local void fraction” . In Proc. Fifth Int. Heat Transfer Conf. Tokyo , , Japan Sep. 3–7, Paper B4.8 1974
   Google Scholar
• Schrock , V. E. and Grossman , L. M. 1959 . Forced Convection Boiling Studies, Forced Convection Vaporization Project , Final Report No. 73308-UCX2182 University of California, Lawrence Radiation Laboratory .
   Google Scholar
• Rohsenow , W. M. and Clark , J. M. 1952 . Heat Transfer and Pressure Drop Data for High Heat Flux Densities in Water at High Sub-Critical Pressure MIT : Institute of Mechanical Engineers Report .
   Google Scholar
• Karoutas , Z. E. , Sung , Y. , Chang , Y. , Kogan , G. A. and Joffre , P. F. 2004 . “Subcooled boiling data from rod bundles” . In Proc. Twelfth Int. Conf. on Nuclear Engineering (ICONE12) Arlington , , USA Apr. 25–29, 2004, Paper 49492
   Google Scholar