Hot-Channel Stability of Supercritical Water-Cooled Reactors—I: Steady-State and Sliding Pressure Startup

References

• J. BUONGIORNO and P. E. MACDONALD, “Supercritical Water Reactor (SCWR) Progress Report for the FY-03 Generation-IV R&D Activities for the Development of the SCWR in the U.S.,” INEEL/EXT-03-01210, Idaho National Engineering and Environmental Laboratory (2003).
   Google Scholar
• N. ZUBER, “An Analysis of Thermally Induced Flow Oscillations in the Near-Critical and Super-Critical Thermodynamic Region,” Nas8-11422, National Aeronautical and Space Administration (1966).
   Google Scholar
• T. NAKATSUKA, Y. OKA, and S. KOSHIZUKA, “Startup Thermal Considerations for Supercritical-Pressure Light Water-Cooled Reactors,” Nucl. Technol., 134, 221 (2001).
   Google Scholar
• S. KOSHIZUKA, Y. OKA, and S. JI, “Stability Analysis of a High Temperature Reactor Cooled by Supercritical Light Water,” GENES4/ANP2003, September 15-19, Kyoto, Japan (2003).
   Google Scholar
• W. S. YANG and N. ZAVALJEVSKI, “Preliminary Investigation of Power-Flow Instability of Supercritical Water Reactor,” Proc. Global 2003, November 16-20, New Orleans, Louisiana (2003).
   Google Scholar
• J. ZHAO, P. SAHA, and M. S. KAZIMI, “One-Dimensional Thermal-Hydraulic Stability Analysis of Supercritical Fluid Cooled Reactors,” ICONE 12-49075, Arlington, Virginia (2004).
   Google Scholar
• “ASME Steam Properties for Industrial Use Based on IAPWS-IF97,” Professional version 1.0.1, American Society of Mechanical Engineers (1998).
   Google Scholar
• W. WAGNER et al., “The IAPWS Industrial Formulation 1997 for the Thermodynamic Properties of Water and Steam,” J. Eng. Gas Turbines Power, 122, 150 (2000).
   Web of Science ®Google Scholar
• X. CHENG and T. SCHULENBERG, “Heat Transfer at Supercritical Pressure—Literature Review and Application to an HPLWR,” FZKA 6609, Forschungszentrum Karlsruhe (2001).
   Google Scholar
• I. L. PIORO, R. B. DUFFEY, and T. J. DUMOUCHEL, “Hydraulic Resistance of Fluids Flowing in Channels at Supercritical Pressures (Survey),” Nucl. Eng. Des., 231, 187 (2004).
   Google Scholar
• G. K. FILONENKO, “Hydraulic Resistance of the Pipelines,” Thermal Eng., 4, 40 (1954) (in Russian).
   Google Scholar
• M. ISHII and N. ZUBER, “Thermally Induced Flow Instabilities in Two Phase Mixtures,” Proc. 4th Int. Heat Transfer Conf., Paper B 5.11, Paris, France (1970).
   Google Scholar
• M. ISHII, “Thermally Induced Flow Instabilities in Two-Phase Mixtures in Thermal Equilibrium,” PhD Thesis, Georgia Institute of Technology (June 1971).
   Google Scholar
• R. T. LAHEY, Jr., and F. J. MOODY, The Thermal-Hydraulics of a Boiling Water Nuclear Reactor, Chap. 7, American Nuclear Society, La Grange Park, Illinois (1993).
   Google Scholar
• J. MARCH-LEUBA and J. M. REY, “Coupled Thermohydraulic-Neutronic Instabilities in Boiling Water Nuclear Reactors: A Review of the State of the Art,” Nucl. Eng. Des., 145, 1-2, 97 (1993).
   Google Scholar
• J. ZHAO, P. SAHA, and M. S. KAZIMI, “Analysis of Flow Instabilities in Supercritical Water-Cooled Nuclear Reactors,” MIT-ANP-TR-105, Massachusetts Institute of Technology (Sep. 2004).
   Google Scholar
• B. PORTER, Stability Criteria for Linear Dynamical Systems, Academic Press, New York (1968).
   Google Scholar
• J. P. HOLMAN, Experimental Methods for Engineers, 7th ed., Chap. 7, McGraw Hill Book Company, New York (2001).
   Google Scholar
• J. ZHAO, “Stability Analysis of Supercritical Water-Cooled Reactors,” PhD Thesis, Massachusetts Institute of Technology (2005).
   Google Scholar
• V. B. KHABENSKY and V. A. GERLIGA, Hydrodynamic Flow Instabilities in Power Equipment Components, pp. 94106, CBS Publishers and Distributors, New Delhi, India (1995).
   Google Scholar
• K. L. YU and B. N. GLUSKER, “Flow Stability Investigation in Parallel Coils with Upflow-Downflow of the Fluid at Subcritical and Supcritical Pressures,” CKTI Proc., 59, 198 (1965).
   Google Scholar
• P. SAHA and N. ZUBER, “Point of Net Vapor Generation and Vapor Void Fraction in Subcooled Boiling,” Proc. 5th Int. Heat Transfer Conf., Paper B4.7, Tokyo, Japan (1974).
   Google Scholar
• P. SAHA, “Thermally Induced Two-Phase Flow Instabilities, Including the Effect of Thermal Non-Equilibrium Between the Phases,” PhD Thesis, Georgia Institute of Technology (June 1974).
   Google Scholar
• D. BESTION, “The Physical Closure Laws in the CATHARE Code,” Nucl. Eng. Des., 124, 229 (1990).
   Web of Science ®Google Scholar
• P. CODDINGTON, and R. MACIAN, “A Study of the Performance of Void Fraction Correlations Used in the Context of Drift-Flux Two-Phase Flow Models,” Nucl. Eng. Des., 215, 199 (2002).
   Web of Science ®Google Scholar
• S. LEVY, “Forced Convection Subcooled Boiling-Prediction of Vapor Volumetric Fraction,” Int. J. Heat Mass Transfer, 10, 951 (1967).
   Web of Science ®Google Scholar
• N. E. TODREAS and M. S. KAZIMI, Nuclear System I, Thermal Hydraulic Fundamentals, Chap. 1, Hemisphere Publishing Corporation (1990).
   Google Scholar
• “Startup Study for SCWR-Generation IV,” Draft 4-5 2004, Burns & Roe Enterprises (2004).
   Google Scholar