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The Design Rationale of the IFR
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Physics Studies of Higher Actinide Consumption in an LMR
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Marseille, France, p, April 23-27
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R. N. HILL, D. C. WADE, E. K. FUJITA, and H. KHALIL, "Physics Studies of Higher Actinide Consumption in an LMR," Proc. Int. Conf. on the Physics of Reactors, Marseille, France, p.I-83, April 23-27 (1990).
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0029378548
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Physics Studies of Weapons Plutonium Disposition in the Integral Fast Reactor Closed Fuel Cycle
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R. N. HILL, D. C. WADE, J. R. LIAW, and E. K. FUJITA, "Physics Studies of Weapons Plutonium Disposition in the Integral Fast Reactor Closed Fuel Cycle," Nuclear Science and Engineering, 121, 17 (1995).
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HILL, R.N.1
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FUJITA, E.K.4
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45149116166
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Preliminary Core Design Studies for the Advanced Burner Reactor over a Wide Range of Conversion Ratios
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E. A. HOFFMAN, W. S. YANG, and R. N. HILL, "Preliminary Core Design Studies for the Advanced Burner Reactor over a Wide Range of Conversion Ratios," Argonne National Laboratory, ANL-AFCI-177 (2006).
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Argonne National Laboratory, ANL-AFCI-177
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HOFFMAN, E.A.1
YANG, W.S.2
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7
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2642548275
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Physics and Safety Studies of Low Conversion Ratio Sodium Cooled Fast Reactors
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New Orleans, Louisiana, United States, pp, November 16-20
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M. A. SMITH, E. E. MORRIS, R. N. HILL, "Physics and Safety Studies of Low Conversion Ratio Sodium Cooled Fast Reactors", Global 2003, New Orleans, Louisiana, United States, pp. 423-433, November 16-20 (2003).
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Global 2003
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SMITH, M.A.1
MORRIS, E.E.2
HILL, R.N.3
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8
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0842312835
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2-2: A Code to Calculate Fast Neutron Spectra and Multi-Group Cross-Sections
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Argonne National Laboratory
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2-2: A Code to Calculate Fast Neutron Spectra and Multi-Group Cross-Sections." ANL-8144, Argonne National Laboratory (1976).
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A User's Guide to the REBUS-3 Fuel Cycle Analysis Capability
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10
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Experience with Advanced Driver Fuels in EBR-II
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C. E. LAHM, J. F. KOENIG, R. G. PAHL, D. L. PORTER, and D. C. CRAWFORD. "Experience with Advanced Driver Fuels in EBR-II," Journal of Nuclear Materials, 204, 119 (1993).
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11
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0027658819
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Status of Fuel, Blanket, and Absorber Testing in the Fast Flux Test Facility
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R. B. BAKER, F. E. BARD, R. D. LEGGETT, and A. L. PINTER, "Status of Fuel, Blanket, and Absorber Testing in the Fast Flux Test Facility," Journal of Nuclear Materials, 204, 109 ( 1993).
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BAKER, R.B.1
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PINTER, A.L.4
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13
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45149084788
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SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation, ORNL/TM-2005/39, Version 5.1, Vols. I-III, November 2006. Available from Radiation Safety Information Computational Center at Oak Ridge National Laboratory as CCC-732
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SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation, ORNL/TM-2005/39, Version 5.1, Vols. I-III, November 2006. Available from Radiation Safety Information Computational Center at Oak Ridge National Laboratory as CCC-732.
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14
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45149090247
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ORIGEN-S: Scale System Module to Calculate Fuel Depletion, Actinide Transmutation, Fission Product Buildup and Decay, and Associated Radiation Source Terms, ORNL/TM-2005/39, Version 5.1, II, Book 1, Sect. F7, November 2006. Available from Radiation Safety Information Computational Center at Oak Ridge National Laboratory as CCC-732
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ORIGEN-S: Scale System Module to Calculate Fuel Depletion, Actinide Transmutation, Fission Product Buildup and Decay, and Associated Radiation Source Terms, ORNL/TM-2005/39, Version 5.1, Vol. II, Book 1, Sect. F7, November 2006. Available from Radiation Safety Information Computational Center at Oak Ridge National Laboratory as CCC-732.
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