63
Views
0
CrossRef citations to date
0
Altmetric
Technical Paper

Production and Characterization of ZrC-UC Inert Matrix Composite Fuel for Gas Fast Reactors

, , &
Pages 200-209 | Published online: 10 Apr 2017

REFERENCES

  • S. Y. LOBACH, T. W. KNIGHT, N. JACOB, and E. ATHON, “Advanced TRISO Fuels with Zirconium Carbide for High Temperature Reactors,” Proc. Global 2007 Advanced Nuclear Fuel Cycles and Systems, Boise, Idaho, September 9–13, 2007, American Nuclear Society (2007).
  • G. VASUDEVAMURTHY, “Composite Nuclear Fuel Fabrication Methodology for Gas Fast Reactors,” PhD Dissertation, University of South Carolina (2007).
  • G. VASUDEVAMURTHY and T. W. KNIGHT, “Effect of System Parameters on Size Distribution of 304 Stainless Steel Particles Produced by Electrical Discharge Mechanism,” Mater. Lett., 61, 27 (2007).
  • G. VASUDEVAMURTHY, T. W. KNIGHT, E. ROBERTS, and T. ADAMS, “Laboratory Production of Zirconium Carbide Compacts for Use in Composite Nuclear Fuels,” J. Nucl. Mater., 347, 1–2, 241 (2008).
  • G. VASUDEVAMURTHY and T. W. KNIGHT, “Production of High Density Uranium Carbide Compacts for Use in Composite Nuclear Fuels,” Nucl. Technol., 163, 2, 321 (2008).
  • “A Technology Roadmap for Generation IV Nuclear Energy Systems Executive Summary,” GIF-001-00, U.S. Department of Energy Nuclear Energy Research Advisory Committee and Generation IV International Forum (GenIV) (2003).
  • T. Q. FOLEY and T. W. KNIGHT, “Fuel Cycle Analysis of GFR Using Advanced Fuels,” Prog. Nucl. Energy, 51, 109 (2009).
  • M. K. MEYER, “Report on the Feasibility of GFR Fuel for Minor Actinide Management,” Argonne National Laboratory West (Aug. 2004).
  • G. R. HARRY, “Status of Steady-State Irradiation Testing of Mixed-Carbide Fuel Designs,” LAUR-83-1248, Los Alamos National Laboratory (1983).
  • R. J. HERBST and R. B. MATTHEWS, “Uranium-Plutonium Carbide as an LMFBR Advanced Fuel,” LA-9259-MS, Los Alamos National Laboratory (1982).
  • A. K. SENGUPTA, U. BASAK, A. KUMAR, H. S. KAMATH, and S. BANERJEE, “Experience on Mixed Carbide Fuels with High Pu Content for Indian Fast Breeder Reactor: An Overview,” J. Nucl. Mater., 385, 161 (2009).
  • K. ANANTHASIVAN, S. ANTHONYSAMY, V. CHANDRAMOULI, I. KALIAPPAN, and P. R. VASUDEVA RAO, “Reprocessing of Carbide Fuels: Conversion of Carbide to Nitride as a Head End Step,” J. Nucl. Mater., 228, 18 (1996).
  • C. L. TRYBUS, J. E. SANECKI, and S. P. HENSLEE, “Casting of Metallic Fuel Containing Minor Actinide Additions,” J. Nucl. Mater., 204, 50 (1993).
  • K. NAKAJIMA, Y. ARAI, and Y. SUZUKI, “Vaporization Behavior of Neptunium Mononitride,” J. Nucl. Mater., 247, 33 (1997).
  • K. NAKAJIMA, Y. ARAI, and Y. SUZUKI, “Vaporization Behavior of (Np,Pu)N,” J. Alloys Compounds, 271–273, 666 (1998).
  • J. P. HIERNAUT and C. RONCHI, “Curium Vaporization from (Cm,Pu)2O3 and from Irradiated Oxide Fuel: Mass Spectrometric Measurement,” J. Nucl. Mater., 334, 2–3, 133 (2004).
  • P. K. SMITH and D. E. PETERSON, “High-Temperature Evaporation and Thermodynamic Properties of Cm2O3,” J. Chemical Phys., 52, 10, 4963 (1970).
  • T. B. LINDEMER, “Thermochemical Analysis of Gas-Cooled Reactor Fuels ContainingAm and Pu Oxides,” ORNL/TM-2002/133, Oak Ridge National Laboratory (2002).
  • L. L. LYON, “Performance of (U, Zr)C-Graphite (Composite) and of (U, Zr)C (Carbide) Fuel Elements in the Nuclear Furnace 1 Test Reactor,” LA-5398-MS, Los Alamos National Laboratory (1973).
  • C. DONOHOUE and J. J. MOORE, “SHS Production of Nitride Nuclear Fuels Using Surrogate Materials,” Trans. Am. Nucl. Soc., 99, 303 (2008).
  • R. FIELDING, M. MEYER, J. JUE, and J. GAN, “Gas-Cooled Fast Reactor Fuel Fabrication,” J. Nucl. Mater., 371, 1–3, 243 (2007).
  • J. JUE and R. FIELDING, “Characterization of Uranium Carbide Spheres for Gas-Cooled Fast Reactors,” Trans. Am. Nucl. Soc., 94, 714 (2006).
  • M. K. MEYER, R. FIELDING, and J. GAN, “Fuel Development for Gas-Cooled Fast Reactors,” J. Nucl. Mater., 371, 1–3, 281 (2007).
  • S. K. MUKERJEE et al., “Kinetic Study of the Carbothermic Synthesis of Uranium Mono-Carbide Microspheres,” J. Nucl. Mater., 172, 37 (1990).
  • E. D. CABANILLAS et al., “Production of Uranium-Molybdenum Particles by Spark Erosion,” J. Nucl. Mater., 324, 1 (2004).
  • “Deep-Burn Modular Helium Reactor Fuel Development Plan,” ORNL/TM-2002/135, Oak Ridge National Laboratory (2002).

Reprints and Corporate Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

To request a reprint or corporate permissions for this article, please click on the relevant link below:

Academic Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

Obtain permissions instantly via Rightslink by clicking on the button below:

If you are unable to obtain permissions via Rightslink, please complete and submit this Permissions form. For more information, please visit our Permissions help page.