The calculation of dryout in a rod bundle
暂无分享,去创建一个
[1] Geoffrey F. Hewitt,et al. STUDIES OF BURNOUT IN BOILING HEAT TRANSFER. , 1967 .
[2] A. E. Bergles,et al. INVESTIGATION OF BOILING FLOW REGIMES AND CRITICAL HEAT FLUX. Quarterly Progress Report, March 6, 1965-June 15, 1965. Report No. 582 , 1965 .
[3] J. Weisman,et al. Methods for detailed thermal and hydraulic analysis of water-cooled reactors , 1975 .
[4] R. W. Wood,et al. BURN-OUT POWER AND PRESSURE DROP MEASUREMENTS ON 12-FT. 7-ROD CLUSTERS COOLED BY FREON-12 AT 155 PSIA. , 1969 .
[5] D. S. Rowe. COBRA-II: A DIGITAL COMPUTER PROGRAM FOR THERMAL-HYDRAULIC SUBCHANNEL ANALYSIS OF ROD BUNDLE NUCLEAR FUEL ELEMENTS. , 1970 .
[6] G. Peterlongo,et al. RESULTS OF WET STEAM COOLING EXPERIMENTS. PRESSURE DROP, HEAT TRANSFER AND BURNOUT MEASUREMENTS WITH ROUND TUBES , 1960 .
[7] Geoffrey F. Hewitt,et al. BURNOUT AND NUCLEATION IN CLIMBING FILM FLOW , 1965 .
[8] G. P. Gaspari,et al. SOME CONSIDERATIONS ON CRITICAL HEAT FLUX IN ROD CLUSTERS IN ANNULAR DISPERSED VERTICAL UPWARD TWO-PHASE FLOW. , 1970 .
[9] Geoffrey F. Hewitt,et al. THE CALCULATION OF CRITICAL HEAT FLUX IN FORCED CONVECTION BOILING , 1974 .
[10] C. W. Gear,et al. The automatic integration of stiff ordinary differential equations , 1968, IFIP Congress.
[11] G. Hewitt,et al. Sampling probe studies of the gas core in annular two-phase flow—II: Studies of the effect of phase flow rates on phase and velocity distribution , 1964 .
[12] W. A. Crago,et al. Liquid film flow‐rates in two‐phase flow of steam and water at 1000 lb./sq. in. abs , 1969 .
[13] G. Wallis. Annular Two-Phase Flow—Part 2: Additional Effects , 1970 .
[14] P. Hutchinson,et al. A possible characterisation of entrainment in annular flow , 1973 .
[15] G. P. Gaspari,et al. Rod-centered subchannel analysis with turbulent (enthalpy) mixing for critical heat flux prediction in rod clusters cooled by boiling water , 1974 .
[16] B. A. Bennett,et al. Flow visualization studies of boiling at high pressure , 1965 .