The Physical State of Post-Loss-of-Coolant Accident Containment Atmospheres

References

• “The Marvikken Full Scale Containment Experiments,” MXB-301, AB Atomenergi (Mar. 1977).
   Google Scholar
• T. F. KANZLEITER, “LOCA Experiments with a PWR Multi-Component Model Containment,” Trans. 1977 LWR Safety Conf., Idaho Falls, Idaho (1977).
   Google Scholar
• R. C. SCHMITT et al., “Simulated Design Basis Accident Tests of the Carolinas Virginia Tube Reactor Containment,” IN-1403, Idaho Nuclear Corp. (1970).
   Google Scholar
• L. C. RICHARDSON, L. J. FINNEGAN, R. J. WAGNER, and J. M. WANGE, “CONTEMPT-A Computer Program for Predicting the Containment Pressure-Temperature Response to a Loss-of-Coolant Accident,” IDO-17-220, Idaho Operations Office, U.S. Atomic Energy Commission (June 1967).
   Google Scholar
• L. L. WHEAT, R. J. WAGNER, G. F. NIEDERANER, and C. F. OBENCHAIN, “CONTEMPT-LT-A Computer Program for Predicting Containment Pressure-Temperature Response to a Loss-of-Coolant Accident,” ANCR-1219, Aerojet Nuclear Company (June 1975).
   Google Scholar
• F. BORDELOU and E. MURPHY, “Containment Pressure Analysis Code (COCO),” WCAP-8326, Westinghouse Electric Corporation (1974).
   Google Scholar
• R. G. GIDO et al., “COMPARE-A Computer Program for the Transient Calculation of a System of Volumes Connected by Flowing Vents,” LA-NUREG-6488 NS, Los Alamos Scientific Laboratory (Sep. 1976).
   Google Scholar
• “Performance and Sizing of Dry Pressure Containments,” BN-TOP-3, Bcchtel Power Corporation (1974).
   Google Scholar
• “The BEACON (Best Estimate Containment Analysis Code),” under development at EG&G, Idaho, Inc.
   Google Scholar
• R. WHITLEY, C. K. CHAN, and D. OKRENT, “On the Analysis of Containment Heat Transfer Following a LOCA,” Anal. Nucl. Eng., 3, 515 (1976).
   Web of Science ®Google Scholar
• W. J. KROTUIK and M. B. RUBIN, “Condensing Heat Transfer Following a Loss-of-Coolant Accident,” Nucl. Technol., 37, 118 (1978).
   Google Scholar
• R. W. BRADY, H. M. SCHOENHOFF, and J. W. THIESING, “Surface Temperature Response of Equipment Inside Containment Following Pipe Break,” Trans. Am. Nucl. Soc., 24, 319 (1976).
   Google Scholar
• D. C. SLAUGTERBECK, “Correlations to Predict the Maximum Containment Pressure Following a LOCA in Large Pressurized Water Reactors with Dry Containments,” TID-4500, U.S. Atomic Energy Commission (May 1971).
   Google Scholar
• H. UCHIDA et al., “Evauation of Post-Incident Cooling Systems of Light Water Power Reactors,” Proc. 3rd Conf. Peaceful Uses At. Energy, A/CONF 28/P/426, United Nations, New York (1965).
   Google Scholar
• S. NAGATA, Mixing Principles and Applications, pp. 207-211, John Wiley and Sons, Inc., New York (1975).
   Google Scholar
• F. J. MOODY, “Fluid Reactor and Impingement Loads,” ASCE Conf. Structural Design, Vol. 1, pp. 219-262, American Society of Civil Engineers (Dec. 1973).
   Google Scholar
• ANSI N176 ANS-58.3 (Draft Jan. 1977).
   Google Scholar
• E. S. LOVE et al., “Experimental and Theoretical Studies of Axisymmetric Free Jets,” NASA-TR-R-G, National Aeronautics and Space Administration (1959).
   Google Scholar
• F. T. BUCKLEY and G. WILLIAMS, “The Prediction of Turbulent Mixing in Moderately Underexpanded Exhaust Plumes,” Tripartite Conf. Plume Signal Interference (May 1972).
   Google Scholar
• S. I. PAI, Fluid Dynamics of Jets, D. Van Nostrand Co., New York (1954).
   Google Scholar
• R. E. HENRY, “The Two-Phase Critical Discharge of Initially Saturated or Subcooled Liquid,” Nucl. Sci. Eng., 41, 337 (1970).
   Google Scholar
• S. OSTRACH and A. KOESTEL, “Film Instabilities in Two-Phase Flows,” AIChE J., 11, 294 (1965).
   Web of Science ®Google Scholar
• G. B. WALLIS, One-Dimensional Two-Phase Flow, pp. 387-397, McGraw-Hill Book Company, New York (1969).
   Google Scholar
• C. W. SAVERY et al., “Water Entrainment in Intercompartment Flow,” EPRI-NP-648, Electric Power Research Institute (Feb. 1978).
   Google Scholar
• A. KOESTEL, J. S. GILBERT, and R. G. GIDO, “Film Entrainment Determination for Containment Subcompartment Flows,” Trans. Am. Nucl. Soc., 29, 406 (1978).
   Google Scholar
• R. BROWN and J. L. YORK, “Sprays Found by Flashing Liquid Jets,” AIChE J., 8, 149 (1962).
   Google Scholar
• M. J. MOORE and C. H. SIEVERING, Two-Phase Steam Flow in Turbines and Separators, Hemisphere Publishing Corporation, Washington, D.C. (1976).
   Google Scholar
• R. G. GIDO and A. KOESTEL, “LOCA-Generated Drop Size Predictions-A Thermal Fragmentation Model,” Trans. Am. Nucl. Sec, 30, 371 (1978).
   Google Scholar
• J. M. MARCHELLO, Control of Air Pollution Sources, Marcel Dekker, Inc., New York (1976).
   Google Scholar
• R. B. BIRD, W. E. STEWART, and E. N. LIGHTFOOT, Transport Phenomena, John Wiley and Sons, Inc., New York (1960).
   Google Scholar
• J. N. CHUNG and P. S. AYYASWAMY, “The Effect of Internal Circulation on the Heat Transfer of a Nuclear Reactor Containment Spray Droplet,” Nucl. Technol., 35, 603 (1977).
   Web of Science ®Google Scholar
• W. RANZ and W. MARSHALL, “Evaporation from Drops,” Chem. Eng. Prog., 4, 141 (1952).
   Google Scholar
• ASME Steam Tables, American Society of Mechanical Engineers (1967).
   Google Scholar
• Shi-Chune YAO and V. E. SCHRÖCK, “Heat and Mass Transfer from Freely Falling Drops,” 75-WA/Mt-37, American Society of Mechanical Engineers (1976).
   Google Scholar
• C. L. HENDERSON and J. M. MARCHELLO, “Film Condensation in the Presence of a Noncondensible Gas,” J. Heat Transfer, 91, 447 (1969).
   Web of Science ®Google Scholar
• T. TAGAMI, “Interim Report on Safety Assessment and Facilities Establishment (SAFE) Project,” Hitachi Ltd., Tokyo (1966).
   Google Scholar
• K. K. ALMENAS and J. M. MARCHELLO, “The Effect of Drop Evaporation Rate on Containment Pressure Transients,” Nucl. Technol., 41, 263 (1978).
   Web of Science ®Google Scholar