Author(s) / Report Title / Publication Number / Date
	B. T. Rearden, "Development of SAMS: A Three-Dimensional Sensitivity Analysis Module for the SCALE Code System," Ph.D. Dissertation, Texas A&M University, College Station, Texas, December 1999.
	R. Q. Wright and W. C. Jordan, "An Approximate Method to Estimate the Minimum Critical Mass of Fissile Nuclides," American Nuclear Society 1999 Winter Meeting, November 14-18, 1999, Long Beach, California.  Trans. Am. Nucl. Soc., 81, 175-178, 1999.
	B. D. Murphy, "Neutronic Design Calculations on Moderators for the Spallation Neutron Source (SNS)," American Nuclear Society 1999 Winter Meeting, November 14-18, 1999, Long Beach, California. Trans. Am. Nucl. Soc., 81, pp. 263-267, November 1999.
	M. E. Dunn, N. M. Greene, and D. F. Hollenbach, "Development and Testing of a New AMPX Cross Section Processing System for Criticality Safety Applications," American Nuclear Society 1999 Winter Meeting, November 14-18, 1999, Long Beach, California. Trans. Am. Nucl. Soc., 81, 160-161, 1999.
	B. L. Broadhead, C. M. Hopper, and C. V. Parks, "Sensitivity and Uncertainty Analysis Applied to Range of Applicability Determination," American Nuclear Society 1999 Winter Meeting, November 14-18, 1999, Long Beach, California. Trans. Am. Nucl. Soc., 81, 172-174, 1999.
	C. W. Forsberg, K. R. Elam, and C. M. Hopper, "Repository Criticality Control for  233U Using Depleted Uranium," American Nuclear Society 1999 Winter Meeting, November 14-18, 1999, Long Beach, California. Trans. Am. Nucl. Soc., 81, 166-167, 1999.
	C. W. Forsberg, C. M. Hopper, and H. C. Vantine, "What Is Non-Weapons-Usable 233U?," American Nuclear Society 1999 Winter Meeting, November 14-18, 1999, Long Beach, California.  Trans. Am. Nucl. Soc., 81, 62-63, 1999.
	E. Greenspan, Y. Karni, D. Regev, and L. M. Petrie, "The SWAN-SCALE Code for Optimization of Critical Systems," American Nuclear Society 1999 Winter Meeting, November 14-18, 1999, Long Beach, California. Trans. Am. Nucl. Soc., 81, 170-171, 1999.
	B. L. Broadhead, C. M. Hopper, and C. V. Parks, Sensitivity and Uncertainty Analyses Applied to Criticality Safety Validation, Volume 2: Illustrative Applications and Initial Guidance, NUREG/CR-6655, Vol. 2 (ORNL/TM-13692/V2), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, November 1999.
	B. L. Broadhead, C. M. Hopper, R. L. Childs, and C. V. Parks, Sensitivity and Uncertainty Analyses Applied to Criticality Safety Validation, Volume 1: Methods Development, NUREG/CR-6655, Vol. 1 (ORNL/TM-13692/V1), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, November 1999.
	B. L. Broadhead and S. M. Bowman, Joint Report of Foreign Travel to Tsukuba, Japan (October 17-21, 1999) and Tokai, Japan (October 25-29, 1999), FTR XA 110619 and 109916, November 1999.
	M. D. DeHart, Report of Foreign Travel to Versailles, France, September  18-25, 1999, FTR XA 107961, October 1999.
	S. M. Bowman, Report of Foreign Travel to Versailles, France, September 18-27, 1999, FTR XA 108030, October 1999.
	D. F. Hollenbach and B. L. Broadhead, Joint Report of Foreign Travel to Paris, France, September  17-25, 1999, FTR XA 108390 and 108019, October 1999.
	C. M. Hopper, Report of Foreign Travel to Versailles, France, September  25-29, 1999, FTR XA 108355, October 1999.
	C. V. Parks, Report of Foreign Travel to Versailles, France, September  13-26, 1999, FTR XA 107864, October 1999.
	R. M. Westfall, Report of Foreign Travel to Boulogne, France and Madrid, Spain, September 7-October 5, 1999, FTR XA 108215, October 1999.
	M. B. Emmett, "MORSE: Present Capabilities and Future Directions," p. 39 in  Proceedings IRRMA'99 Meeting, 4th Topical Meeting on Industrial Radiation and Radioisotope Measurement Applications, October 3-7, 1999, Raleigh, North Carolina. [Abstract]
	M. D. DeHart, "A Deterministic Study of the Deficiency of the Wigner-Seitz Approximation for Pu/MOX Fuel Pins," pp. 689-699 in  Proceedings M&C'99-Madrid, Mathematics and Computations Meeting, September 27-30, 1999, Madrid, Spain.
	S. M. Bowman, J. E. Horwedel, D. L. Barnett, and L. M. Petrie,  "SCALE Graphical Developments for Improved Criticality Safety Analyses," Vol. I, pp. 278-287 in Proceedings ICNC'99, Sixth International Conference on Nuclear Criticality Safety, September 20-24, 1999, Palais des Congres, Versailles, France.
	B. L. Broadhead, R. L. Childs, and B. T. Rearden, "Computational Methods for Sensitivity and Uncertainty Analysis in Criticality Safety," Vol. I, pp. 57-65 in Proceedings ICNC'99, Sixth International Conference on Nuclear Criticality Safety, September 20-24, 1999, Palais des Congres, Versailles, France.
	B. L. Broadhead, C. M. Hopper, and C. V. Parks, "Proposed Methodology for Establishing Area of Applicability," Vol. II, 787-798 in  Proceedings ICNC'99, Sixth International Conference on Nuclear Criticality Safety, September 20-24, 1999, Palais des Congres, Versailles, France.
	M. D. DeHart and B. L. Broadhead, "Investigation of Burnup Credit Issues in BWR Fuel," Vol. II, pp. 586-595 in  Proceedings ICNC'99, Sixth International Conference on Nuclear Criticality Safety, September 20-24, 1999, Palais des Congres, Versailles, France.
	D. F. Hollenbach and W. C. Jordan, "An Analysis of the HEU-MET-FAST-035 Problem Using CENTRM and SCALE," Vol. II, pp. 828-834 in  Proceedings ICNC'99, Sixth International Conference on Nuclear Criticality Safety, September 20-24, 1999, Palais des Congres, Versailles, France.
	C. M. Hopper, B. L. Broadhead, R. L. Childs, and C. V. Parks, "Slide Rule for Rapid Response Estimation of Radiological Dose from Criticality Accidents," Vol. III, pp. 1334-1344 in  Proceedings ICNC'99, Sixth International Conference on Nuclear Criticality Safety, September 20-24, 1999, Palais des Congres, Versailles, France.
	C. M. Hopper, K. R. Elam, C. V. Parks, and J. J. Lichtenwalter, "Bounding Values for Low-Level-Waste Transport Exemptions and Disposal," Vol. I, pp. 438-446 in  Proceedings ICNC'99, Sixth International Conference on Nuclear Criticality Safety, September 20-24, 1999, Palais des Congres, Versailles, France.
	R. Q. Wright, W. C. Jordan, and L. C. Leal, "Fast and Thermal Data Testing of U-233 Critical Assemblies," Vol. I, pp. 340-347 in  Proceedings ICNC'99, Sixth International Conference on Nuclear Criticality Safety, September 20-24, 1999, Palais des Congres, Versailles, France.
	O. W. Hermann, San Onofre PWR Data for Code Validation of MOX Fuel Depletion Analyses, ORNL/TM-1999/108, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, September 1999.
	M. D. DeHart, Parametric Analysis of PWR Spent Fuel Depletion Parameters for Long-Term Disposal Criticality Safety, ORNL/TM-1999/99, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, August 1999.
	R. L. Childs, SEN1: A One-Dimensional Cross-Section Sensitivity and Uncertainty Module for Criticality Safety Analysis, NUREG/CR-5719 (ORNL/TM-13738), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, July 1999.
	S. M. Bowman, SCALE Newsletter, No. 20, July 1999.
	L. C. Leal, O. W. Hermann, S. M. Bowman, and C. V. Parks, "Automatic Rapid Process for the Generation of Problem-Dependent SAS2H/ORIGEN-S Cross-Section Libraries,"  Nucl. Technol., 127, 1-23, July 1999.
	C. V. Parks, B. T. Rearden, M. D. DeHart, B. L. Broadhead, C. M. Hopper, and L. M. Petrie, Annual Environmental Management Science Program (EMSP) Summary Progress Report. Project Title: "Development of Nuclear Analysis Capabilities for DOE Waste Management Activities," ORNL/TM-1999/101, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, June 1999.
	L. E. Toran, C. M. Hopper, C. V. Parks, and V. A. Colten-Bradley, The Potential for Criticality Following Disposal of Uranium at Low-Level Waste Facilities, Volume 2: Containerized Disposal, NUREG/CR-6505, Vol. 2 (ORNL/TM-13323/V2), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, June 1999.
	M. E. Dunn and P. B. Fox, Criticality Safety Scoping Study for the Transport of Weapons-Grade Mixed-Oxide Fuel Using the MO-1 Shipping Package, ORNL/TM-13741, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, May 1999.
	M. E. Dunn and N. M. Greene, Testing of Multi-pole Formalism and POLIDENT Continuous Energy Cross-Section Data for Criticality Safety Applications, ORNL/NRC/LTR-99/9, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, May 1999.
	C. F. Weber and E. C. Beahm, Calculation of pH and Iodine Volatility Under Reactor Accident Conditions, ORNL/NRC/LTR-99/3, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, March 1999.
	S. M. Bowman and J. E. Horwedel,  "KENO3D Visualization Tool for KENO V.a Geometry Models,"  Trans. Am. Nucl. Soc., 80, 158-159 (1999).
	M. D. DeHart, "A Deterministic Study of Deficiencies in the Wigner-Seitz Cell Approximation,"  Trans. Am. Nucl. Soc., 80, 149-151 (1999).
	M. E. Dunn, N. M. Greene, and L. C. Leal, "Energy Meshing Techniques for Processing ENDF/B-VI Cross Sections Using the AMPX Code System,"  Trans. Am. Nucl. Soc., 80, 140-142 (1999).
	C. M. Hopper, "Applicable Ranges, DOE's Nuclear Criticality Safety Program, DNFSB 97-2, Panel Discussion/Round Table participants,"  Trans. Am. Nucl. Soc., 80, 157 (1999).
	R. M. Westfall, "Analytical Methods, DOE's Nuclear Criticality Safety Program, DNFSB 97-2, Panel Discussion/Round Table participants," Trans. Am. Nucl. Soc., 80, 157 (1999).
	R. Q. Wright, W. C. Jordan, and L. C. Leal, "Fast and Thermal Data Testing of 233U Critical Assemblies," Trans. Am. Nucl. Soc., 80, 134-135 (1999).
	C. M. Hopper and K. R. Elam, Proposed Outline for Guidance Documentation Emplacement Criticality Guidance for Low-Level Waste Disposal, ORNL/M-6637, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, January 1999.
	C. F. Weber and E. C. Beahm, Iodine Revolatilization in a Grand Gulf LOCA, ORNL/M-6544, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, January 1999.
	C. F. Weber, E. C. Beahm, and J. S. Watson, "Modeling Thermodynamics and Phase Equilibria for Aqueous Solutions of Trisodium Phosphate,"  J. Sol. Chem. Vol. 28, No. 11, 1207-1238, (1999).