Author(s) / Report Title / Publication Number / Date
	J. A. Bucholz, A Master Library of High-Energy Measurements from the Lawrence Livermore National Laboratory Pulsed Sphere Experiment Program, ORNL/TM-2003/92, UT-Battelle, LLC, Oak Ridge National Laboratory, December 2003.
	J. A. Bucholz, Updated MCNP Analyses of High-Energy Measurements from the Lawrence Livermore National Laboratory Pulsed Sphere Experiment Program, ORNL/TM-2003/121, UT-Battelle, LLC, Oak Ridge National Laboratory, December 2003.
	S. M. Bowman, D. F. Hollenbach, M. D. DeHart, B. T. Rearden, I. C. Gauld, and S. Goluoglu, "SCALE 5: Powerful New Criticality Safety Analysis Tools," pp. 447-453 in  Proc. of The 7th International Conference on Nuclear Criticality Safety (ICNC2003)," October 20-24, 2003, Tokai-mura, Japan.
	S. M. Bowman and J. E. Horwedel, "New SCALE Graphical Interface for Criticality Safety," pp. 516-522 in  Proc. of The 7th International Conference on Nuclear Criticality Safety (ICNC2003)," October 20-24, 2003, Tokai-mura, Japan.
	M. E. Dunn, N. M. Greene, and L. M. Petrie, "Continuous-energy Version of KENO V.a for Criticality Safety Applications,"pp. 439-446 in  Proc. of The 7th International Conference on Nuclear Criticality Safety (ICNC2003)," October 20-24, 2003, Tokai-mura, Japan.
	J. C. Wagner, "Evaluation of Burnup Credit for Accommodating PWR Spent Nuclear Fuel in High-capacity Cask Designs," pp. 684-689 in Proc. of The 7th International Conference on Nuclear Criticality Safety (ICNC2003)," October 20-24, 2003, Tokai-mura, Japan.
	B. T. Rearden, C. M. Hopper, K. R. Elam, S. Goluoglu, and C. V. Parks, "Applications of the TSUNAMI Sensitivity and Uncertainty Analysis Methodology," pp. 61-66 in  Proc. of The 7th International Conference on Nuclear Criticality Safety (ICNC2003)," October 20-24, 2003, Tokai-mura, Japan.
	K. R. Elam, Criticality Safety Study of UF6 and UO2F2 in 8-in.-Diameter Piping, ORNL/TM-2003/239, UT-Battelle, LLC, Oak Ridge National Laboratory, October 2003.
	M. D. DeHart, Z. Zhong, and T. J. Downar, "TRITON: An Advanced Lattice Code for MOX Fuel Calculations," 14-01.pdf in  Proc. of American Nuclear Society, Advances in Nuclear Fuel Management III, October 5-8, 2003, Hilton Head Island, South Carolina.
	W. J. Anderson, M. Saglam, B. T. Rearden, and R. Smith, "Reactor Physics and Criticality Benchmark Evaluations for Advanced Nuclear Fuel: Experiment Analysis Comparison Report," 09-031.pdf in  Proc. of American Nuclear Society, Advances in Nuclear Fuel Management III, October 5-8, 2003, Hilton Head Island, South Carolina.
	K. R. Elam, J. C. Wagner, and C. V. Parks,  Effects of Fuel Failure on Criticality Safety and Radiation Dose for Spent Fuel Casks, NUREG/CR-6835 (ORNL/TM-2002/255), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, September 2003.
	I. C. Gauld, MOX Cross-Section Libraries for ORIGEN-ARP, ORNL/TM-2003/2, UT-Battelle, LLC, Oak Ridge National Laboratory, July 2003.
	S. M. Bowman and M. D. DeHart, Joint Report of Foreign Travel to Paris, France, June 18 - 28, 2003, FTR XA 170461 and 170462, July 2003.
	S. M. Bowman,  SCALE Newsletter, No. 28, July 2003.
	I. C. Gauld, Report of Foreign Travel to Stockholm & Oskarshamn, Sweden, May 13 - 21, 2003, FTR XA 169789, June 2003.
	I. C. Gauld,  Strategies for Application of Isotopic Uncertainties in Burnup Credit, NUREG/CR-6811 (ORNL/TM-2001/257), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, June 2003.
	Sedat Goluoglu, C. M. Hopper, and B. T. Rearden, "Extended Interpretation of Sensitivity Data for Benchmark Areas of Applicability," in Proc. of ANS 2003 Annual Meeting "The Nuclear Technology Expansion: Unlimited Opportunities," June l-5, 2003, San Diego, California. Trans. Am. Nucl. Soc., 88, 77-79 ( 2003).
	Y. Karni, D. Regev, E. Greenspan, S. Goluoglu, L. M. Petrie, and C. M. Hopper, "On the SMORES Capability for Minimum Critical Mass Determination," in  Proc. of ANS 2003 Annual Meeting "The Nuclear Technology Expansion: Unlimited Opportunities," June l-5, 2003, San Diego, California. Trans. Am. Nucl. Soc., 88, 82-83 (2003).
	R. D. Busch and S. M. Bowman, "The KENO V.a Primer," in Proc. of ANS 2003 Annual Meeting "The Nuclear Technology Expansion: Unlimited Opportunities," June l-5, 2003, San Diego, California. [Summary]. Trans. Am. Nucl. Soc., 88, 80-81 (2003).
	D. F. Hollenbach, Report of Foreign Travel to Port Hope, Ontario, Canada, March 30 - April 5, 2003, FTR XA 168308, May 2003.
	B. L. Broadhead, Recommendations for Shielding Evaluations for Transport and Storage Packages, NUREG/CR-6802 (ORNL/TM-2002/31), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, May 2003.
	M. E. Dunn, PUFF-III: A Code for Processing ENDF Uncertainty Data into Mulitgroup Covariance Matrices, NUREG/CR-6650 (ORNL/TM-1999/235), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, April 2003.
	L. C. Leal and M. E. Dunn, "A New Approach for Calculating Average Cross Sections in the Unresolved Energy Region," 109.pdf in  Proc. of Nuclear Mathematical and Computational Sciences: A Century in Review, A Century Anew,  April 6-11, 2003, LaGrange Park, Illinois (2003).
	Herschel P. Smith and J. C. Wagner, "A Case Study in Manual and Automated Monte Carlo Variance Reduction with a Deep Penetration Reactor Shielding Problem,"  050.pdf in  Proc. of Nuclear Mathematical and Computational Sciences: A Century in Review, A Century Anew,  April 6-11, 2003, LaGrange Park, Illinois (2003). ISBN0-89448-674-8, American Nuclear Society Order No. 700300.
	Z. Zhong, T. Downar, and M. DeHart, "Benchmarking the U.S. NRC Neutronic Codes NEWT and PARCS with the VENUS-2 MOX Critical Experiments ," 097.pdf in  Proc. of Nuclear Mathematical and Computational Sciences: A Century in Review, A Century Anew,  April 6-11, 2003, LaGrange Park, Illinois (2003).
	J. C. Wagner, M. D. DeHart, and C. V. Parks, Recommendations for Addressing Axial Burnup in PWR Burnup Credit Analyses, NUREG/CR-6801 (ORNL/TM-2001/273), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, March 2003.
	C. V. Parks and C. J. Withee, "Recommendations for PWR Storage and Transportation Casks That Use Burnup Credit,"  pp. 500-507 in Proc. of American Nuclear Society 2003 10th International High-Level Radioactive Waste Management (IHLRWM) Conference, "Progress Through Cooperation,"  March 30-April 2, 2003, Las Vegas, Nevada (2003).
	F. C. Difilippo, "Monte Carlo Calculations of Pebble Bed Benchmark Configurations of the PROTEUS Facility," Nuc. Sci. Eng., Vol. 143, No. 3, March 2003, pp. 240-253.
	J. C. Wagner and C. E. Sanders,  Assessment of Reactivity Margins and Loading Curves for PWR Burnup-Credit Cask Designs, NUREG/CR-6800 (ORNL/TM-2002/6), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, March 2003.
	J. C. Wagner and C. V. Parks,  Recommendations on the Credit for Cooling Time in PWR Burnup Credit Analyses, NUREG/CR-6781 (ORNL/TM-2001/272), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, January 2003.
	C. E. Sanders and I. C. Gauld,  Isotopic Analysis of High-Burnup PWR Spent Fuel Samples From the Takahama-3 Reactor, NUREG/CR-6798 (ORNL/TM-2001/259), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, January 2003.
	A. Haghighat and John C. Wagner, "Monte Carlo Variance Reduction with Deterministic Importance Functions," Progress in Nuclear Energy, 42(1), 25-53 (January 2003).
	R. D. Busch and S. M. Bowman,  KENO V.a Primer: A Primer for Criticality Calculations with SCALE/KENO V.a Using CSPAN for Input, ORNL/TM-2002/155, UT-Battelle, LLC, Oak Ridge National Laboratory, January 2003.
	S. M. Bowman,  SCALE Newsletter, No. 27, January 2003.