[1] James C S and James K A. Nuel Eng Inter, 1986, 31, 83–86.[2] Moskal T E, Childerson M T, Carter H R. Amer Contr Conf,1984, 1: 85–92.[3] Heistand J W and Thakkar J G. ATHOS and FLOW3 simulationof the FRIGG heated rod bundle experiment, TechnicalReport NP-3541, EPRI, 1984.[4] Yetisir M, Pietralik J, Mirzai M. Pres Ves P, 2003, 2: 61–69.[5] Xue H J and Yan J Q. Nucl P Eng, 1989, 10: 47–50. (in Chinese)[6] Xie H, Zhang J L, Jia D N, et al. Nucl P Eng, 1998, 19: 413–418. (in Chinese)[7] Yu Y and Ju H M. J Tsinghua Univ (Sci &Tech), 2004, 44:1202–1204. (in Chinese)[8] Kazimi M and Massoud M. A condensed review of nuclearreactor thermal-hydraulic computer codes for two-phaseflow analysis. Energy Laboratory Report No. MIT-EL 79-018,February 1980, 37–40.[9] IAPWS, Revised release on the IAPWS industrial formulation1997 for the thermodynamic properties of water and steam[OL]. Aug. 2007, available at http://www.iapws.org.[10] Taitel Y, Bornea D, Dukler A E. Aiche J, 1980, 26: 345–354.[11] Lockhart R W and Martinelli R C. Chem Eng Prog, 1949, 1:39–48.[12] Chen J C. Ind Eng Chem Proc DD, 1966, 5: 531–535.[13] Bergles A E and Rohsenow W M. J Heat Transf, 1964, 86:365–372.[14] NUREG/CR-5535/Rev P3-Vol IV, Relap5 mod3.3 code manualvolume IV: models and correlations, prepared for the Officeof Nuclear Regulatory Research, US NRC, Washington DC,2006, 42. |