Development of GAMMA Code as an Integrated Code Analyzing a Coupled Very High Temperature Gas-Cooled Reactor and Hydrogen Production Plant

References

• C. H. OH, R. BARNER, C. DAVIS, and S. SHERMAN, “Evaluation of Working Fluids in an Indirect Combined Cycle in a Very High Temperature Gas-Cooled Reactor,” Nucl. Technol., 156, 1 (2006).
   Web of Science ®Google Scholar
• P. E. MACDONALD et al., “The Next Generation Nuclear Plant—Insights Gained from the INEEL Point Design Studies,” INEEL/CON-04-01563, Idaho National Laboratory (2004).
   Google Scholar
• “Gas Turbine-Modular Helium Reactor (GT-MHR) Conceptual Design Description Report,” 910720, Revision 1, General Atomics (July 1996).
   Google Scholar
• D. R. NICHOLLS, “Status of the Pebble Bed Modular Reactor,” Nucl. Energy, 39, 4, 231 (2000).
   Google Scholar
• S. SAITO, T. TANAKA, Y. SUDO, O. BABA, S. SHUSAKU, and M. OKUBO, “Design and Safety Consideration in the High-Temperature Engineering Test Reactor (HTTR),” IAEA-TC-389, International Atomic Energy Agency (2000).
   Google Scholar
• Z. WU, D. LIN, and D. ZHONG, “The Design Features of the HTR-10,” Nucl. Eng. Des., 218, 25 (2002).
   Web of Science ®Google Scholar
• SCDAP0RELAP5-3D CODE DEVELOPMENT TEAM, SCDAP/RELAP5-3D Code Manual, Volume 2: Modeling of Reactor Core and Vessel Behavior During Severe Accidents, INEEL-EXT-02-00589, Revision 2.2, Idaho National Laboratory (Oct. 2003).
   Google Scholar
• MELCOR Computer Code Manuals, Vol. 2: Material Properties (MP) Package Reference Manual, NUREG/CR-6119, SAND-97-2398, Sandia National Laboratories (1997).
   Google Scholar
• C. H. OH, C. DAVIS, L. SIEFKEN, R. MOORE, H. C. NO, J. KIM, G. C. PARK, J. C. LEE, and W. R. MARTIN, “Development of Safety Analysis Codes and ExperimentalValidation for a Very High Temperature Gas-Cooled Reactor,” Final Report, INL/EXT-06-01362, Idaho National Laboratory (Mar. 2006).
   Google Scholar
• T. POINSOT and D. VEYNANTE, Theoretical and Numerical Combustion, R. T. Edwards Inc., Flourtown, Pennsylvania (2001).
   Google Scholar
• D. A. NIELD and A. BEJAN, Convection in Porous Media, Springer-Verlag, New York (1999).
   Google Scholar
• J. P. HOLMAN, Heat Transfer, 6th ed., McGraw-Hill Book Company, New York (1986).
   Google Scholar
• J. O. HIRSCHFELDER, C. F. CURTISS, and R. B. BIRD, Molecular Theory of Gases and Liquids, John Wiley & Sons, New York (1964).
   Google Scholar
• W. M. KAYES and M. E. CRAWFORD, Convective Heat and Mass Transfer, 2nd ed., McGraw-Hill Book Company, New York (1980).
   Google Scholar
• B. E. POLING, J. M. PRAUSNITZ, and J. P. O’CONNELL, The Properties of Gases and Liquids, 5th ed., McGraw-Hill Book Company, New York (2001).
   Google Scholar
• K. RAZNJEVIC, Handbook of Thermodynamic Tables and Charts, Hemisphere Publishing Company, Washington (1976).
   Google Scholar
• F. H. HARLOW and A. A. AMSDEN, “A Numerical Fluid Dynamics Calculation Method for All Flow Speeds,” J. Comput. Phys., 8, 197 (1971).
   Web of Science ®Google Scholar
• J. B. DUNCAN and H. L. TOOR, “An Experimental Study of Three Component Gas Diffusion,” AIChE J., 8, 1, 38 (1962).
   Web of Science ®Google Scholar
• C. H. OH, E. S. KIM, H. C. NO, and N. Z. CHO, “Experimental Validation of Stratified Flow Phenomena, Graphite Oxidation, and Mitigation Strategies of Air Ingress Accidents,” INL/EXT-08-14840, Idaho National Laboratory (2008).
   Google Scholar
• J. H. KIM, H. M. KIM, and H. C. NO, “Assessment of HTGR Helium Compressor Analysis Tool Based on Newton-Ralphson Numerical Application to Throughflow Analysis,” Proc. Int. Conf. Nuclear Engineering (ICONE 14), Miami, Florida, July 17–20, 2006, 89411, American Society of Mechanical Engineers (2006).
   Google Scholar
• N. A. CUMPSTY, Compressor Aerodynamics, Longman Scientific & Technical, Harlow, United Kingdom (1989).
   Google Scholar
• J. D. DENTON, “Throughflow Calculation for Transonic Axial Flow Turbines,” J. Eng. Power, 100, 212 (1978).
   Google Scholar
• T. TAKIZUKA, S. TAKATA, X. YAN, S. KOSUGIYAMA, S. KANTANISHI, and K. KUMITOMI, “R&D on the Power Conversion System for Gas Turbine High Temperature Reactors,” Nucl. Eng. Des., 233, 329 (2004).
   Web of Science ®Google Scholar
• INDEPENDENT TECHNOLOGY REVIEW GROUP, “Design Features and Technology Uncertainties for the Next Generation Nuclear Plant,” INEEL/EXT-04-01816, Idaho National Laboratory (2004).
   Google Scholar
• C. H. OH, C. B. DAVIS, J. HAN, R. BARNER, S. SHERMAN, R. VILIM, Y. LEE, and W. LEE, “HyPEP FY06 Report: Models and Method,” INL/EXT-06-11725, Idaho National Laboratory (Sep. 2006).
   Google Scholar
• I. SOCHET, J. L. ROUYER, and P. HEMMERICH, “Safe Hydrogen Generation by Nuclear HTR,” Paper 4261, Proc. Int. Congress Advances in Nuclear Power Plants (ICAPP ’04), Pittsburgh, Pennsylvania, June 13–17, 2004, American Nuclear Society (2004).
   Google Scholar
• C. S. SMITH, S. BECK, and B. GALYEAN, “An Engineering Analysis for Separation Requirements of a Hydrogen Production Plant and High-Temperature Nuclear Reactor,” INL/EXT-05-00137 Rev. 0, Idaho National Laboratory (Mar. 2005).
   Google Scholar
• “HYSYS Process Version 2.2.2.,” Aspen Technology; available on the Internet at www.aspentech.com (2005).
   Google Scholar