References
- K. V. MOORE et al, RETRAN–A Program for One-Dimensional Transient Thermal-Hydraulic Analysis of Complex Fluid Flow Systems, EPRI CCM-5, Vols. 1-4, Electric Power Research Institute (1978).
- R. W. LYCZKOWSKI et al., “The Development of RELAP/SLIP for the Semiscale Blowdown Heat Transfer Test S-02-6,” EPRI NP-343, Electric Power Research Institute (1976).
- K. V. MOORE et al., “RETRAN–A Program for One-Dimensional Transient Thermal-Hydraulic Analysis of Complex Fluid Flow Systems, Volume 1: Equations and Numerics,” EP NP-408, Electric Power Research Institute (1977).
- C. W. SOLBRIG and E. D. HUGHES, “Governing Equations for a Seriated Continuum: An Unequal Velocity Model for Two-Phase Flow,” ANCR-1193, Aerojet Nuclear Company (1975).
- C. W. SOLBRIG, G. A. MORTENSEN, and R. W. LYCZKOWSKI, “An Unequal Phase Velocity, Unequal Temperature Theory Applied to Two-Phase Blowdown from a Horizontal Pipe,” in Proc: 25th Heat Transfer and Fluid Mechanics Institute, Davis, California, June 21-23, 1976, pp. 60-76, Stanford Press, Stanford, California (1976).
- E. D. HUGHES, R. W. LYCZKOWSKI, J. H. McFADDEN, and G. F. NIEDERAUER, “An Evaluation of State-of-the-Art Two-Velocity Two-Phase Flow Models and Their Applicability to Nuclear Reactor Transient Analysis,” EPRI NP-143, Electric Power Research Institute (1976).
- E. D. HUGHES and R. K. FUJITA, “Comparisons of RETRAN and Two-Velocity Two-Phase Flow Models with Experimental Data,” EPRI NP-928, Electric Power Research Institute (1978).
- C. W. SOLBRIG, J. H. McFADDEN, R. W. LYCZKOWSKI, and E. D. HUGHES, “Heat Transfer and Friction Correlations Required to Describe Steam-Water Behavior in Nuclear Safety Studies,” presented at the 15th National Heat Transfer Conference, San Francisco, August 10-13, 1975, Paper No. 21. Available on microfiche from Oak Ridge National Laboratory as CONF-75084 3 (1976).
- A. W. BENNETT, G. F. HEWITT, H. A. KEARSEY, R. K. F. KEEYS, and P. M. C. LACEY, “Flow Visualization Studies of Boiling Water at High Pressure,” AERE-R 4874, Atomic Energy Research Establishment (1965).
- M. SEVIK and S. H. PARK, “The Splitting of Drops and Bubbles by Turbulent Fluid Flow,” J. Fluids Eng., 95, 53 (1973).
- E. O. MOECK, “Annular-Dispersed Two-Phase Flow and Critical Heat Flux,” AECL-3656, Atomic Energy of Canada Limited (1970).
- F. E. MARBLE, “Some Gasdynamic Problems in the Flow of Condensing Vapors,” Astronaut. Acta, 14, 585 (1969).
- G. B. WALLIS, “Annular Two-Phase Flow–Part 1: A Simple Theory,” ASME Preprint 69-FE-45, American Society of Mechanical Engineers (1969).
- G. B. WALLIS, “Annular Two-Phase Flow–Part 2: Additional Effects,” ASME Preprint 69-FE-46, American Society of Mechanical Engineers (1969).
- V. H. RANSOM, R. J. WAGNER, J. A. TRAPP, K. E. CARLSON, D. M. KISER, and H. H. KUO, “RELAP5/MOD0 Code Description,” CDAP-TR-057, EG&G Idaho (1979).
- D. NYLUND et al., “Hydrodynamic and Heat Transfer Measurements on a Full-Scale Simulated 36-Rod Marviken Fuel Element with Uniform Heat Flux Distribution,” FRIGG-2(1968).
- B. L. COLLINS et al., “Experiment Data Report for Semiscale Mod-1, Test S-02-6 (Blowdown Heat Transfer Test),” TREE-NUREG-1037, U.S. Atomic Energy Commission (1977).
- G. R. SAWTELLE and G. L. MINNER, “Semiscale Small Break Analysis with RETRAN,” Proc. Topi. Mtg. Thermal Reactor Safety, Knoxville, Tennessee, April 6-9, 1980, CONF-800403, II, 1205 (1980).