REFERENCES
- R. WIGELAND and T. BAUER, “Repository Benefits of AFCI Options,” ANL-AFCI-129, Argonne National Laboratory (2004).
- J. LAMARSH, Introduction to Nuclear Reactor Theory, Addison-Wesley, Reading, Massachusetts (1966)
- C. TILL, Y. CHANG, and W. HANNUM, “The Integral Fast Reactor—An Overview,” Prog. Nucl. Energy, 31, 1–2, 3 (1997).
- E. MORRIS and M. SMITH, “Development of Low Conversion Ratio Fast Reactors for Transmutation,” ANL-AAA-057, Argonne National Laboratory (2002).
- D. WADE and R. HILL, “The Design Rationale of the IFR,” Prog. Nucl. Energy, 31, 1–2, 13 (1997).
- E. HOFFMAN, W. YANG, and R. HILL, “Preliminary Core Design Studies for the Advanced Burner Reactor over a Range of Conversion Ratios,” ANL-AFCI-177, Argonne National Laboratory (2006).
- M. SMITH, E. MORRIS, and R. HILL, “Physics and Safety Studies of a Low Conversion Ratio Sodium Cooled Fast Reactor,” Proc. Global ’03, New Orleans, Louisiana, November 16–20, 2003, American Nuclear Society (2003).
- A. DUBBERLY, K. YOSHIDA, C. BOARDMAN, and T. WU, “Superprism Oxide and Metal Fuel Core Designs,” Proc. Int. Conf. Nuclear Engineering (ICONE-8), Baltimore, Maryland, April 2–6, 2000.
- K. WIRTZ, Lectures on Fast Reactors, American Nuclear Society, La Grange Park, Illinois (1982)
- V. BERTHOU, C. DEGUELDRE, and J. MAGILL, “Transmutation Characteristics in Thermal and Fast Neutron Spectra: Application to Americium,” J. Nucl. Mater., 320, 156 (2003).
- F. MANN and R. SCHENTER, “Calculated Neutron Capture Cross Sections to the Americium Ground and Isomeric States,” Nucl. Sci. Eng., 63, 242 (1977).
- M. ROME, A. HARISLUR, E. HERNIOU, A. ZAETTA, and J. TOMMASI, “Use of Fast Reactors to Burn Long-Life Actinides, EspeciallyAm, Produced by Current Reactors,” Proc. Physor ’96, confMito, Japan, September 16–20, 1996.
- M. ROME, A. HARISLUR, and E. HERNIOU, “Study of Once-Through Americium Matrices Strategy in Fast Reactors,” Proc. ICONE-5, Nice, France, May 26–30, 1997.
- K. FUJIMURA, T. SANDA, M. MAYUMI, S. MORO, M. SAITO, and H. SEKIMOTO, “Feasibility Study of LargeMOX Fueled FBR Core Aimed at the Self-Consistent Nuclear Energy System,” Prog. Nucl. Energy, 37, 1–4, 177 (2000).
- K. FUJIMURA, T. SANDA, M. YAMAWAKI, and K. KNASHI, “Enhancement of Transmutation Characteristics of the Minor Actinide Burning Fast Reactor Core Concept Using Hydride Fuel Targets and Its Introduction Scenario,” J. Nucl. Sci. Technol., 38, 10, 879 (2001).
- K. MOORE and W. YOUNG, “Phase Studies of the Zr-H System at High Hydrogen Concentrations,” J. Nucl. Mater., 27, 316 (1968).
- “Design and Demonstration of the UREX + Process Using Spent Nuclear Fuel,” Proc. Advances for Future Nuclear Fuel Cycles (ATALANTE 2004), Nimes, France, June 21–24, 2004.
- G. HOFMAN, L. WALTERS, and T. BAUER, “Metallic Fast Reactor Fuels,” Prog. Nucl. Energy, 31, 1–2, 83 (1997).
- B. HILTON, D. PORTER, and S. HAYES, “AFC-1 Transmutation Fuels Post-Irradiation Hot Cell Examination 4 to 8 at. %: Final Report,” INL/EXT-05-00785, Idaho National Laboratory (2006).
- J. ACKERMAN, T. JOHNSON, and J. LAIDLER, “Waste Removal in Pyrochemical Fuel Processing for the Integral Fast Reactor,” Proc. Int. Symp. Actinides: Processing & Materials, San Francisco, California, February 27–March 3, 1994.
- A. STANCULESCU. J. GARNIER, J. ROUAULT, E. KIEFHABER, and R. SUNDERLAND, “Plutonium Burning and Minor Actinides Transmutation in Fast Reactors: First Results Obtained Within the Frame of the CAPRA Program,” Proc. Int. Nuclear Congress: Atoms for Energy, Lyon, France, October 2–6, 1994.
- A. VASILE, G. RIMPAULT, J. TOMMASI, C. DE SAINT JEAN, M. DELPECH, K. HESKETH, H. BEUAMONT, R. SUNDERLAND, T. NEWTON, P. SMITH, W. MASCHEK, D. HAAS, C. RAEDT, G. VAMBENEPE, and J. LEFEVRE, “Fast Reactors Fuel Cycle Core Physics Results from the CAPRACADRA Programme,” Proc. Global ’01, Paris, France, September 13–17, 2001.
- H. HENRYSON II, B. TOPPEL, and C. STENBERG, “MC2-2:ACode to Calculate Fast Neutron Spectra and Multi-Group Cross-Sections,” ANL-8144, Argonne National Laboratory (1976).
- K. DERSTINE, “DIF3D:ACode to Solve One-, Two-, and Three-Dimensional Finite-Difference Diffusion Theory Problems,” ANL-82-64, Argonne National Laboratory (1984).
- B. TOPPEL, “AUser’s Guide to the REBUS-3-3 Fuel Cycle Analysis Capability,” ANL-83-2, Argonne National Laboratory (1983).
- D. HAMRIN, “SCALE: A Modular Code System for Performing Standard Computer Analysis for Licensing Evaluation,” ONRNL/TM-2005/39, Oak Ridge National Laboratory (2006).
- X-5MONTE CARLO TEAM, “MCNP5—AGeneral Monte Carlo N-Particle Transport Code: Version 5,” LA-UR-03-1987, Los Alamos National Laboratory (2003).
- D. GELLES, “Microstructural Development in Reduced Activation Ferritic Alloys Irradiated to 200 dpa at 420C,” J. Nucl. Mater., 212–215, 714 (1994).
- L. WALTERS and J. KITTLE, “Development and Performance of Metal Fuel Elements for Fast Breeder Reactors,” Nucl. Technol., 48, 273 (1980).
- L. WALTERS and B. SEIDEL, “Performance of Metallic Fuels and Blankets in Liquid-Metal Fast Breeder Reactors,” Nucl. Technol., 65, 179 (1984).