A Dynamic Model for Predicting CANDU Pressurizer Performance

References

• D. B. BOSLEY, R. S. LEDDICK, and Ε. Ε. DRUCKER, “A Fundamental Approach to the Analysis of Steam Surge-Tank Transients”, ASME Paper No. 57-A-269, American Society of Mechanical Engineers (1957).
   Google Scholar
• T. H. GLASSER, “Basic Equations for Predicting Performance of a Nuclear Power Plant Pressurizer”, ASME Paper No. 57-NESC-95, Proc. 2nd Nuclear Engineering and Science Conf., American Society of Mechanical Engineers (1957).
   Google Scholar
• D. H. BROWN, “Transient Thermodynamics of Reactors and Process Apparatus”, ASME Paper No. 57-NESC-81, Proc. 2nd Nuclear Engineering and Science Conf., American Society of Mechanical Engineers (1957).
   Google Scholar
• J. M. GALLAGHER, Jr., “A Procedure for Determining Pressurizer Design Parameters,” WCAP-563, Westinghouse Electric Commercial Atomic Power (1957).
   Google Scholar
• F. PAXTON, “Curtis-Wright Pressurizer Study”, WR-400-20, Curtis Research Division (1959).
   Google Scholar
• J. P. CUNNINGHAM and H. R. MEYER, “PRESTO-A Pressurizer Transient Program for the IBM-704”, YAEC-141, Westinghouse Electric Atomic Power Department (1960).
   Google Scholar
• A. W. THOMAS and J. FINDLY, “PRE-A Pressurizer Transient Program for the Pilco 2000 Computer”, KAPL-ME7-7, Knolls Atomic Power Laboratory (1961).
   Google Scholar
• P. L. BRADLEY, “Development and Design Studies of SM-2 Pressurizer”, APAE-Memo-266, Alco Products Inc. (1960).
   Google Scholar
• E. E. DRUCKER and K. N. TONG, “Behavior of a Steam Pressurizer Surge-Tank,” Trans. Am. Nucl. Soc., 5, 1 (1962).
   Google Scholar
• E. E. DRUCKER and K. W. TONG, “The Compression of Initially Saturated Vapors”, ME761-790-A, Syracuse University Research Institute (1960).
   Google Scholar
• J. A. REDFIELD and S. G. MARGOLIS, “TOPS-A Fortran Program for the Transient Thermodynamics of Pressurizers”, WAPD-TM-545, Bettis Atomic Power Laboratory (1965).
   Google Scholar
• J. A. REDFIELD, V. PRESCOP, and S. G. MARGOLIS, “Pressuriser Performance During Loss-of-Load Tests at Shippingport: Analysis and Test,” Nucl. Appl., 4, 173 (1968).
   Google Scholar
• V. C. ROHATGI, P. SAHA, and A. A. DUBOW, “Lumped-Parameter Modeling of PWR Downcomer and Pressurizer for LOCA Conditions”, presented at the ENS/ANS Int. Topi. Mtg. Nuclear Power Reactor Safety, Brussels, Belgium, October 16–19, 1978.
   Google Scholar
• D. J. GORMAN and R. K. GUPTA, “The Analysis and Computation of Steam Surge Tank Pressure Transients”, presented at Int. Conf. Pressure Surges, Paper No. 3, University of Kent, Canterbury, England, September, 1972.
   Google Scholar
• T. F. CHANG, “A Thermal-Hydraulic System Simulation Model for the Reactor, Boiler and Heat Transport System (SOPHT)”, CNS-37-2, University of Chicago Metallurgical Laboratory (1977).
   Google Scholar
• K. V. MOORE et al., “RETRAN-4-Program for One Dimensional Transient Thermal-Hydraulic Analysis of Complex Fluid Flow Systems”, EPRI-CCM-5, Vols. 1-4, Electric Power Research Institute (1978).
   Google Scholar
• M. J. P. MAXANT and M. H. PERRIN, “Mathematical Modelling of Two-Phase Flow Applied to Nuclear Power Plants,” Proc. 2nd Conf. Multiphase Transport, Fundamentals, Reactor Safety and Applications, Miami, Florida (1979).
   Google Scholar
• A. B. WAHBA, V. T. BERTA, and W. POINTER, “Pressurizer and Steam Generator Behaviour Under PWR Transient Conditions,” Proc. 3rd Multiphase Flow and Heat Transfer Symp., Miami, Florida, April 18–20, 1983 (1983); also available as AGQG-M-04483.
   Google Scholar
• K. V. MOORE and W. H. RETTING, “RELAP4—A Computer Program for Transient Thermal Hydraulic Analysis”, ANCR-1127, Aerojet Nuclear Company (1973).
   Google Scholar
• V. H. RAWSOM et al., “RELAP5/MOD1, Code Manual Volume 1: System Models and Numerical Methods”, NUREG/CR-1826, EGG-2070, EG&G Idaho, Inc. (Mar 1982).
   Google Scholar
• S. M. SAMI, “A Proposed Model to Simulate Surge Tank and Bleed Condensers in CANDU Reactors”, Rapport techniques GAN-35, Groupe d’Analyse Nucléaire, École Polytechnique (June 1984).
   Google Scholar
• J. F. WILSON, R. J. GRANDA, and J. F. PATTERSON, “Steam Volume Fraction in a Bubbling Two-Phase Mixture,” Trans. Am. Nucl. Soc., 4, 356 (1961).
   Google Scholar
• E. R. ECKERT and R. J. DRAKE, Jr., Heat and Mass Transfer, 2nd ed., McGraw-Hill Book Company, Inc. (1959).
   Google Scholar
• W. H. MCADAMS, Heat Transmission, p. 219, McGraw-Hill Book Company (1954).
   Google Scholar
• W. C. REYNOLDS, “Heat Transfer to Fully Developed Laminar Flow in Circular Tubes with Arbitrary Cir-cumferential Heat Flux”, ASME paper No. 59-HT-13, American Society of Mechanical Engineers (1959).
   Google Scholar
• H. R. SAEDI, “Insurge Pressure Response and Heat Transfer for PWR Pressurizer”, MS Thesis, Massachusetts Institute of Technology (1982).
   Google Scholar
• M. V. BONACA, “PWR Transient Pressurizer Pressure Behavior,” Trans. Am. Nucl. Soc., 39, 1024 (1981).
   Google Scholar
• E. E. MERLO, H. S. RAGHEB, and K. A. BOW, “HYDNA-3 Program Description”, TDAI-205, Atomic Energy of Canada Limited (Apr 1980).
   Google Scholar
• Y. F. CHANG and J. SHERIN, “SOPHT-B Verification, Bruce NGS-A Turbine Load Rejection Test from 83% FP”, 1979, Proc. Symp. Simulation of Reactor Dynamics and Plant Control, April 1979.
   Google Scholar