Transport Phenomena in Supercritical Fluids in Gen-IV Reactor Designs

References

• A. ZILLMER, “The Effect of Supercritical Water on Ferritic and Austenitic Steel Alloys,” MS Thesis, University of Wisconsin-Madison (2004).
   Google Scholar
• M. DECKERS et al., “Modern Steam Turbines for Ultra-Supercritical Steam Power Plants,” Proc. World Engineers’ Convention, Shanghai, China, November 2–6, 2004, China Association for Science and Technology (2004).
   Google Scholar
• Y. OKA and S.-I. KOSHIZUKA, “Concept and Design of a Supercritical-Pressure, Direct-Cycle Light Water Reactor,” Nucl. Technol., 103, 295 (1993).
   Web of Science ®Google Scholar
• “Generation IV Nuclear Energy Systems Roadmap,” Technical Working Group Reports, U.S. Department of Energy (2002).
   Google Scholar
• R. DUFFEY et al., “Designing High-Efficiency Reactors Using Existing Ultra-Supercritical Technology,” Proc. 3rd Int. Symp. Supercritical Water-Cooled Reactors, Shanghai, China, March 12–15, 2007, Shanghai Jiao Tong University (2007).
   Google Scholar
• G. E. McCREERY, J. BUONGIORNO, K. G. CONDIE, D. M. McELIGOT, M. E. NITZEL, and J. E. O’BRIEN, “The INEEL Heat Transfer Flow Loop For Development Of Supercritical-Pressure Water Reactors (SCWRs),” Proc. Int. Conf. Global Environment and Advanced Nuclear Power Plants (GENES4/ANP2003), Kyoto, Japan, September 15–19, 2003, Atomic Energy Society of Japan (2003).
   Google Scholar
• D. SQUARER et al., “High Performance Light Water Reactor (HPLWR),” Summary Report of the HPLWR Project, HPLWR D 13, European Commission (2002).
   Google Scholar
• J. CLEVELAND et al., “Proposed IAEA Coordinated Research Programme,” International Atomic Energy Agency (May 2006).
   Google Scholar
• P. HEJZLAR, M. POPE, W. WILLIAMS, and M. DRISCOLL, “Gas Cooled Fast Reactor for Generation IV,” Proc. 1st Int. Symp. Innovation Nuclear Energy Systems (COE-INES), Tokyo, Japan, October 31–November 4, 2004, Tokyo Institute of Technology (2004).
   Google Scholar
• J. KESTIN et al., “Thermophysical Properties of Fluid H2O,” J. Phys. Chem. Ref. Data, 13, 175 (1984).
   Web of Science ®Google Scholar
• R. JAIN and M. CORRADINI, “A Linear Stability Analysis for Natural-Circulation Loops Under Supercritical Conditions,” Nucl. Technol., 155, 312 (2006).
   Web of Science ®Google Scholar
• N. ZUBER et al., “An Analysis of Thermally Induced Flow Oscillations in the Near-Critical and Supercritical Thermodynamic Region,” NASA Report NAS8-11422, National Aeronautics and Space Administration (1967).
   Google Scholar
• G. YADIGAROGLU and A. E. BERGLES, “Fundamental and Higher Mode Density Wave Oscillations in Two-Phase Flow,” J. Heat Transfer, 94, 189 (1972).
   Web of Science ®Google Scholar
• V. CHATOORGOON, “Stability of Supercritical Fluid Flow in a Single-Channel Natural-Convection Loop,” Int. J. Heat Mass Transfer, 44, 1963 (2001).
   Web of Science ®Google Scholar
• J. LICHT et al., “SupercriticalWater Heat Transfer,” Proc. 12th Int. Mtg. Nuclear Reactor Thermal Hydraulics (NURETH-12), Pittsburgh, Pennsylvania, September 30–October 4, 2007, American Nuclear Society (2007).
   Google Scholar
• S. LOMPERSKI et al., “Stability of a Natural Circulation Loop for a Fluid Heated Through the Thermodynamic Psuedocritical Point,” Proc. 2004 Int. Congress Advances in Nuclear Power Plants (ICAPP ’04), Pittsburgh, Pennsylvania, June 13–17, 2004, American Nuclear Society (2004).
   Google Scholar
• V. DOSTAL, P. HEJZLAR, and M. J. DRISCOLL, “High-Performance Supercritical Carbon Dioxide Cycle for Next-Generation Nuclear Reactors,” Nucl. Technol., 154, 265 (2006).
   Web of Science ®Google Scholar
• V. DOSTAL, P. HEJZLAR, and M. J. DRISCOLL, “The Supercritical Carbon Dioxide Power Cycle: Comparison to Other Advanced Power Cycles,” Nucl. Technol., 154, 283 (2006).
   Web of Science ®Google Scholar
• D. H. LEE et al., “Evaluation of Critical Flow for Supercritical Steam-Water,” EPRI-NP-3086, Electric Power Research Institute (1983).
   Google Scholar
• J. H. McFADDEN et al., “RETRAN-02: A Program for Transient Thermal-Hydraulic Analysis of Complex Fluid Flow Systems,” Vol. 1, Rev. 2, NP-1850-CCMA, Electric Power Research Institute (1984).
   Google Scholar
• R. SPAN and W. WAGNER, “A New Equation of State for Carbon Dioxide Covering the Fluid Region from the Triple-Point Temperature to 1100 K at Pressures up to 800 MPa,” J. Phys. Chem. Ref. Data, 25, 1509 (1996).
   Web of Science ®Google Scholar
• S. A. KLEIN, “EES: Engineering Equation Solver,” Professional Version 6.738, University of Wisconsin-Madison (2003).
   Google Scholar
• G. MIGNOT et al., “Critical Flow Phenomena for Supercritical CO2,” Proc. 12th Int. Mtg. Nuclear Reactor Thermal Hydraulics (NURETH-12), Pittsburgh, Pennsylvania, September 30–October 4, 2007, American Nuclear Society (2007).
   Google Scholar
• J. D. JACKSON and W. B. HALL, “Forced Convection Heat Transfer to Fluids at Supercritical Pressure,” Turbulent Forced Convection in Channels and Bundles, pp. 563–611, Hemisphere Publishing Corporation, New York (1979).
   Google Scholar
• J. D. JACKSON and W. B. HALL, “Influences of Buoyancy on Heat Transfer to Fluids Flowing in Vertical Tubes Under Turbulent Conditions,” Turbulent Forced Convection in Channels and Bundles, pp. 613–640, Hemisphere Publishing Corporation, New York (1979).
   Google Scholar
• I. PIORO, F. HUSSAM, and R. DUFFEY, “Heat Transfer at Supercritical Pressure,” Proc. 11th Int. Conf. Nuclear Engineering (ICONE-11), Tokyo, Japan, April 20–23, 2003, p. 1, Japan Society of Mechanical Engineers (2003).
   Google Scholar
• K. W. SEO, M. H. KIM, M. H. ANDERSON, and M. L. CORRADINI, “Heat Transfer in a Supercritical Fluid: Classification of Heat Transfer Regimes,” Nucl. Technol., 154, 335 (2006).
   Web of Science ®Google Scholar
• M. ANDERSON, J. LICHT, and M. CORRADINI, “Progress on the University of Wisconsin Supercritical Water Heat Transfer Facility,” Proc. 11th Int. Topl. Mtg. Nuclear Reactor Thermal Hydraulics (NURETH-11), Avignon, France, October 2–6, 2005, French Nuclear Energy Society (2005).
   Google Scholar
• “Status of DOE’s Effort to Develop the Next Generation Nuclear Plant,” U.S. Government Accountability Office (Sep. 2006).
   Google Scholar