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Technical Paper

Study of Solid Moderators for the Thermal-Spectrum Supercritical Water-Cooled Reactor

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Pages 282-303 | Published online: 10 Apr 2017

References

  • “A Technology Roadmap for the Generation IV Nuclear Energy Systems,” GIF-002-00, Generation IV International Forum-2002
  • K. KATAOKAet al., “Development Project of Supercritical-Water Cooled Power Reactor,” Proc. Int. Congress on Advanced Nuclear Power Plants (ICAPP), Hollywood, Florida, June 9-13, 2002, American Nuclear Society (2002).
  • N. J. SPINKS et al., “Thermo-Economic Assessment of Advanced, High-Temperature CANDU Reactors,” Proc. 10th Int. Conf. Nuclear Engineering (ICONE-10), Arlington, Virginia, April 14-18, 2002, American Society of Mechanical Engineers (2002).
  • D. SQUARER et al., “High Performance Light Water Reactor (HPLWR),” HPLWR D 13, European Commission (Oct. 2002).
  • J. BUONGIORNO and P. 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-03-03-01210, Idaho National Engineering and Environmental Laboratory (Sep. 2003).
  • Y. OKA, S. KOSHIZUKA, Y. ISHIWATARI, and A. YAMAJI, “Overview of Design Studies of High temperature Reactor Cooled by Supercritical Light Water at the University of Tokyo,” Proc. GENES4/ANP2003, Kyoto, Japan, September 15-19, 2003.
  • X. CHENG and T. SCHULENBERG, “Thermal-Hydraulic Analysis of Supercritical Light Water Reactors,” Proc. Int. Congress on Advanced Nuclear Power Plants (ICAPP), Hollywood, Florida, June 9-13, 2002, American Nuclear Society (2002).
  • T. HATTORI, H. ANADA, K. ABE, and M. HARADA, “Study of Fuel Cladding Materials for Supercritical-Pressure, Light-Water-Cooled Reactor,” Proc. 1st Int. Symp. Supercritical Water-Cooled Reactors, Design and Technology, The University of Tokyo, November 6-9, 2000.
  • “MCNP4B: Monte Carlo N-Particle Transport Code System,” Los Alamos National Laboratory, CCC-660, Oak Ridge National Laboratory (Apr. 1997).
  • J. J. DUDERSTADT and L. J. HAMILTON, Nuclear Reactor Analysis, p. 563, John Wiley & Sons, New York (1976).
  • “Feasibility Study of Supercritical Light Water Cooled Fast Reactors for Electric Power Production,” NERI Project 2001001, 2nd Annual Report, INEEL/EXT-03-01277, Idaho National Laboratory (Sep. 2003).
  • R. A. KNIEF, Nuclear Engineering, p. 262, Hemisphere Publishing Corporation, New York (1992).
  • R. S. BABCOCK, D. E. WESSOL, C. A. WEMPLE, and S. C. MASON, “The MOCUP Interface: A Coupled Monte Carlo/Depletion System,” Proc. 1994 Topl. Mtg. Advances in Reactor Physics, Knoxville, Tennessee, April 11-15, 1994, Vol. III, American Nuclear Society (1994).
  • A. G. CROFF, “ORIGEN2—A Revised and Updated Version of the Oak Ridge Isotope Generation and Depletion Code,” ORNL-5621, Oak Ridge National Laboratory (July 1980).
  • R. VAN HOUTEN, “Selected Engineering and Fabrication Aspects of Nuclear Metal Hydrides (Li, Ti, Zr and Y),” Nucl. Eng. Des., 31, 434 (1974).
  • W. M. MUELLER, “Hydrides in Nuclear Reactor Applications,” Metal Hydrides, p. 21, Academic Press, New York (1968).
  • C. L. HUFFINE, “Fabrication of Hydrides,” Metal Hydrides, p. 675, Academic Press, New York (1968).
  • M. T. SIMNAD, “The U-ZrHx Alloy: Its Properties and Use in TRIGA Fuel,” Nucl. Eng. Des., 64, 403 (1981).
  • P. PAETZ and K. LUCKE, “Uber die Dichteanderung von Zirkonhydrid bei der Bestrahlung mit Schnellen Neutronen,” J. Nucl. Mater., 43, 13 (1972).
  • V. I. SHCHERBAK, A. PINCHUK, and V. TARASIKOV, “Radiation-Induced Swelling of Zirconium Hydride,” At. Energ., 71, 2, 178 (1991).
  • N. G. PRIMAKOV, V. RUDENKO, V. KAZARNIKOV, and A. BESPALOV, “Nonuniform Swelling and Hydrogen Redistribution in Zirconium Hydride Under Neutron Irradiation,” Int. J. Hydrogen Energy, 24, 805 (1999).
  • S. YAMANAKA et al., “Thermal and Mechanical Properties of Zirconium Hydride,” J. Alloys and Compounds, 293-295, 23 (1999).
  • P. G. PINCHUK et al., “Nature and Thermal Stability of Radiation-Induced Defects in Zirconium Hydride,” At. Energ., 40, 4, 289 (1976).
  • S. YAMANAKA et al., “Thermal Properties of Zirconium Hydride,” J. Nucl. Mater., 294, 94 (2001).
  • J. P. BLACKLEDGE, “Chemistry of Metal Hydrides as Related to Their Applications in Nuclear Technology,” Metal Hydrides, p. 119, Academic Press, New York (1968).
  • W. WANG and D. R. OLANDER, “Thermodynamics of the H-Zr System,” J. Am. Ceram. Soc., 78, 12, 3323 (1995).
  • T. NAMBA et al., “Surface Processes of Hydrogen Transport in Fusion Reactor Materials,” J. Nucl. Mater., 128, 646 (1984).
  • “Guide to Good Practices at DOE Tritium Facilities,” EG&G Mound Applied Technologies (Oct. 1989).
  • J. HUANG, B. TSUCHIYA, K. KONASHI, and M. YAMAKAWI, “Estimation of Hydrogen Redistribution in Zirconium Hydride Under Temperature Gradient,” J. Nucl. Sci. Technol., 37, 10, 887 (2000).
  • D. R. OLANDER, “Fundamental Aspects of Nuclear Reactor Fuel Elements,” Report TID-26711-P1, Technical Information Center, U.S. Department of Energy (1976).Metals Handbook, Vol. 1, ASM International (1990).
  • “Control of Combustible Gas Concentrations in Containment,” Draft Regulatory Guide DG-1117, U.S. Nuclear Regulatory Commission (Aug. 2002).
  • W. J. APLEY, “Tritium Target Development Project Executive Summary Topical Report,” PNL-8142, Pacific Northwest Laboratory (Sep. 1992).
  • S. C. MARSCHMAN et al., “Tritium Permeation Scoping Experiments,” PNL-7843, Pacific Northwest Laboratory (Oct. 1991).
  • D. D. LANNING et al., “Final Report on the WC-1 Light-Water Reactor Target Rod Irradiation Test and Postirradiation Examinations,” Vol. 1, PNL-8133, Pacific Northwest Laboratory (Aug. 1992).
  • B. SIEGEL and G. G. LIBOWITZ, “The Covalent Hydrides and Hydrides of the Groups V to VIII Transition Metals,” Metal Hydrides, p. 545, Academic Press, New York (1968).
  • W. M. MUELLER, “Titanium Hydrides,” Metal Hydrides,p. 336, Academic Press, New York (1968).
  • J. HE, S. FUKUYAMA, K. YOKOGAWA, and A. KIMURA, “Effect of Hydrogen on Deformation of Inconel 718,” Mater. Trans., 35, 10, 689 (1994).
  • S. LENHART, C. HALBACH, W. CULLEN, G. GREWAL, N. PRUITT, and K. GARR, “Hydrogen Environment Embrittlement of Inconel Alloy 718 Pressure Vessels in Ni/H2 Cells,” Proc. Conf. 27th Intersociety Energy Conversion Engineering (IECEC-92), San Diego, California, August 3-7, 1992, Vol. 1, p. 233, Society of Automotive Engineers Inc. (1992).
  • S. GROSS, “The Problem of Hydrogen Embrittlement in Nickel Hydrogen Cells,” Proc. 25th Intersociety Energy Conversion Engineering (IECEC-90), Reno, Nevada, August 12-M. MUELLER, 17, 1990, Vol. 3, p. 33, American Institute of Chemical Engineers (1990).
  • R. P. ELLIOTT, Constitution of Binary Alloys, First Supplement, p. 679, McGraw-Hill Book Company, New York (1965).
  • “INEEL Reusable Property, Recyclable Materials, and Waste Acceptance Criteria (RrWaC),” DOE/ID-10381, Rev. 11, Idaho National Engineering and Environmental Laboratory (June 2000).
  • R. L. BECK and W. M. MUELLER, “Zirconium Hydrides and Hafnium Hydrides,” Metal Hydrides, p. 241, Academic Press, New York (1968).
  • Allegheny Technologies, private communication (July 2002).
  • Alloy Metals & Tubes International, private communication (Sep. 2002).
  • Dynamic Metal Forming, private communication (July 2002).
  • C. S. PARK and G. P. SHARP-BETTE, Advanced Engineering Economics, p. 48, John Wiley & Sons, New York (1990).
  • Y. OKA and S. KOSHIZUKA, “Design Concept of Once-Through Cycle Supercritical-Pressure Light Water Cooled Reactors,” Proc. 1st Int. Symp. Supercritical Water-Cooled Reactors, Design and Technology, The University of Tokyo, November 6-9, 2000.
  • R. VISWANATHAN and W. T. BAKKER, “Materials for Boilers in Ultra Supercritical Power Plants,” Proc. 2000 Int. Joint Power Generation Conf., Miami Beach, Florida, July 23-36, 2000.
  • N. E. TODREAS and M. S. KAZIMI, Nuclear Systems I. Thermal Hydraulic Fundamentals, Chap. 8, Hemisphere Publishing Corporation, New York (1990).
  • S. KOSHIZUKA and Y. OKA, “Computational Analysis of Deterioration Phenomena and Thermal Hydraulic Design of SCR,” Proc. 1st Int. Symp. Supercritical Water-Cooled Reactors, Design and Technology, The University of Tokyo, November 6-9, 2000.
  • Y. ISHIWATARI, Y. OKA, and S. KOSHIZUKA, “Safety Analysis of a High Temperature Supercritical Pressure Light Water Cooled and Moderated Reactor,” Proc. Int. Congress on Advanced Nuclear Power Plants (ICAPP), Hollywood, Florida, June 9-13, 2002, American Nuclear Society (2002).
  • “Alloy 718 Technical Data Sheet,” Allvac, available on the Internet at http://www.allvac.com/pages/Nickel/UNSN07718.htm (2002).

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