Author(s) / Report Title / Publication Number / Date
	E. C. Beahm, C. F. Weber, J. L. Collins, B. Z. Egan, and C. W. Chase,  Sludge Washing and Dissolution of ORNL Melton  Valley Storage Tank (MVST) Waste: Third Interim Letter Report, ORNL/M-4022, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1995.
	E. C. Beahm, C. F. Weber, J. L. Collins, B. Z. Egan, and C. W. Chase,  Washing and Dissolution of Actinides from Melton Valley Storage Tank (MVST) Waste: Interim Letter Report, ORNL/M-4081, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1995.
	C. M. Hopper, "Elements of a Nuclear Criticality Safety Program," Nucl. Safety 36(2),  234-242 (1995).
	J. S. Tang,  Report of Foreign Travel, ORNL/FTR-5292, 1995.
	R. M. Westfall,  The 1993 and 1994 Annual Criticality Review Committee Appraisals, ORNL/CF-95/59, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1995.
	M. J. Haire and W. C. Jordan,  Relative Risk of Nuclear Criticality Occurring from Low-Enriched Uranium and High-Enriched Uranium Deposits at the K-25 Site, Oak Ridge, Tennessee, K/ER-215, Lockheed Martin Energy Systems, Inc., Oak Ridge K-25 Site, December 1995.
	C. V. Parks and B. L. Broadhead, "Review of Criticality Safety and Shielding Analysis Issues for Transportation Packages," PATRAM'95, December 3-8, 1995, Las Vegas, Nevada.
	Y. Y. Liu and J. S. Tang, "Analysis of Radiation Measurement Data of the BUSS Cask," PATRAM'95, December 3-8, 1995, Las Vegas, Nevada.
	C. W. Forsberg, R. B. Pope, R. C. Ashline, M. D. DeHart, K. W. Childs, and J. S. Tang,  DUSCOBS - A Depleted-Uranium Silicate Backfill for Transport, Storage and Disposal of Spent Nuclear Fuel, ORNL/TM-13045, Martin Marietta Energy Systems, Oak Ridge National Laboratory, November 1995.
	C. V. Parks, Report of Foreign Travel to Japan, ORNL/FTR-5616, November 1995.
	M. D. DeHart and S. M. Bowman,  Analysis of Fresh Fuel Critical Experiments Appropriate for Burnup Credit Validation, ORNL/TM-12959, Lockheed Martin Energy Systems, Inc., Oak Ridge National Laboratory, October 1995.
	C. V. Parks, Report of Foreign Travel to Austria and Ukraine, October 1995.
	B. D. Murphy, Report of Foreign Travel to Versailles, France, ORNL/FTR-5570, October 1995.
	B. Basoglu, C. Bentley, M. Dunn, S. Goluoglu, L. Paschal, H. Dodds, and D. Hollenbach, "Evaluation of Several Parallel Algorithms for KENO V.a," 1995 Winter Meeting American Nuclear Society, October 29-November 2, 1995, San Francisco, California.   Trans. Am. Nucl. Soc., 73, 183-184 (1995).
	S. M. Bowman and B. L. Broadhead, "Dose Rates in the ABWR Upper Drywell for a Dropped Fuel Bundle Accident," 1995 Winter Meeting American Nuclear Society, October 29-November 2, 1995, San Francisco, California.   Trans. Am. Nucl. Soc., 73, 364-366 (1995).
	M. D. DeHart, O. W. Hermann, and C. V. Parks, "Validation of SCALE Depletion Methods for PWR Spent Fuel Isotopic Characterization," 1995 Winter Meeting American Nuclear Society, October 29-November 2, 1995, San Francisco, California.   Trans. Am. Nucl. Soc., 73, 361-363 (1995).
	J. S. Tang and B. L. Broadhead,  "Applications of SAS4 Monte Carlo Shielding Sequence to Deep- Penetration Problems," 1995 Winter Meeting American Nuclear Society, October 29-November 2, 1995, San Francisco, California.  Trans. Am. Nucl. Soc., 73,  363-364 (1995).
	B. L. Broadhead and C. V. Parks,   "Overview of SCALE System Shielding Capabilities," 1995 Winter Meeting American Nuclear Society, October 29-November 2, 1995, San Francisco, California. Trans. Am. Nucl. Soc., 73, 360-361 (1995).
	C. M. Hopper, W. C. Jordan, and D. F. Hollenbach,  "Calculated Neutron Spectra for Heterogeneous U(93) and CH2 Critical Assemblies," 1995 Winter Meeting American Nuclear Society, October 29-November 2, 1995, San Francisco, California.  Trans. Am. Nucl. Soc., 73, 220-222 (1995).
	M. L. Williams, M. Asgari, and R. Q. Wright,  "ENDF/B-VI Performance for Thermal Reactor Analysis," 1995 Winter Meeting American Nuclear Society, October 29-November 2, 1995, San Francisco, California.   Trans. Am. Nucl. Soc., 73, 420-22 (1995).
	C. V. Parks, W. C. Jordan, L. M. Petrie, and R. Q. Wright,  "Use of Metal/Uranium Mixtures to Explore Data Uncertainties," 1995 Winter Meeting American Nuclear Society, October 29-November 2, 1995, San Francisco, California. Trans. Am. Nucl. Soc., 73, 217-218 (1995).
	E. C. Beahm, C. F. Weber, J. L. Collins, B. Z. Egan, and C. W. Chase, "Washing and Dissolution of Melton Valley Storage Tank Sludge at Oak Ridge National Laboratory," 9th Symp. on Separation Science and Technology for Energy Applications, October 22-26, 1995, Gatlinburg, Tennessee.
	M. D. DeHart and C. V. Parks,  "Issues Related to Criticality Safety Analysis for Burnup Credit Applications," ICNC'95, Fifth International Conference on Nuclear Criticality Safety, September 17-21, 1995, Albuquerque, New Mexico.
	M. D. DeHart, O. W. Hermann, and C. V. Parks, "Validation of a Method for Prediction of Isotopic Concentrations in Burnup Credit Applications," ICNC'95, Fifth International Conference on Nuclear Criticality Safety, September 17-21, 1995, Albuquerque, New Mexico.
	L. C. Leal, R. M. Westfall, W. C. Jordan, and R. Q. Wright, "Nuclear Data Needs for Application in Nuclear Criticality Safety Programs," pp. 2-3–2-10 in Proc. of the Fifth International Conference on Nuclear Criticality Safety, ICNC’95, September 17 – 21, 1995, Albuquerque, New Mexico.
	D. F. Hollenbach, S. M. Bowman, L. M. Petrie, and C. V. Parks,  "New Enhancements to SCALE for Criticality Safety Analysis," ICNC'95, Fifth International Conference on Nuclear Criticality Safety, September 17-21, 1995, Albuquerque, New Mexico.
	S. M. Bowman, R. Q. Wright, M. D. DeHart, and C. V. Parks, "Recent Validation Experience with Multigroup Cross-Section Libraries and SCALE at ORNL," ICNC'95, Fifth International Conference on Nuclear Criticality Safety, September 17-21, 1995, Albuquerque, New Mexico.
	B. L. Broadhead, R. L. Childs, and C. M. Hopper, "Verification of Criticality Accident Alarm System for Environmental Restoration Activities," ICNC'95, Fifth International Conference on Nuclear Criticality Safety, September 17-21, 1995, Albuquerque, New Mexico.
	R. Q. Wright and W. C. Jordan,  "ENDF/B-VI Chlorine Evaluation is Deficient," ICNC'95, Fifth International Conference on Nuclear Criticality Safety, September 17-21, 1995, Albuquerque, New Mexico.
	S. Raman and B. D. Murphy,  "US/UK Actinides Experiment at the Dounreay PFR, I. Fission Products," Global 95 International Conference on Evaluation of Emerging Nuclear Fuel Cycle Systems, September 11-14, 1995, Versailles, France.
	C. V. Parks,  Report of Foreign Travel, ORNL/FTR-5478, August 1995.
	J. S. Tang,  Report of Foreign Travel, July 17- August 14, 1995, ORNL/FTR-5505, 1995.
	C. V. Parks, R. Q. Wright, and W. C. Jordan,  Adequacy of the 123-Group Cross-Section Library for Criticality Analyses of Water-Moderated Uranium Systems NUREG/CR-6328 (ORNL/TM-12970), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, August 1995.
	R. Q. Wright, J. P. Renier, and J. A. Bucholz,  ANSL-V: ENDF/B-V Based Multigroup Cross-Section Libraries for Advanced Neutron Source Reactor Studies, Supplement 1,  ORNL-6618/s1, Lockheed Martin Energy Systems, Inc., Oak Ridge National Laboratory, August 1995.
	B. L. Broadhead, Report of Foreign Travel to England, ORNL/FTR-5424, July 1995.
	S. Raman, B. D. Murphy, C. W. Nestor, Jr., C. C.  Foreman, W. S. Fraser, and T. D. Newton,  Dounreay PFR Irradiation History for the Joint US/UK Actinide Sample Exposures,  ORNL/TM-12984, Martin Marietta Energy Systems, Oak Ridge National Laboratory, July 1995.
	S. M. Bowman, C. V. Parks, and S. K. Martin, "Maintaining SCALE as a Reliable Computational System for Criticality Safety Analysis," 1995 Annual Meeting American Nuclear Society, June 25-29, 2005, Philadelphia, Pennsylvania. Trans. Am. Nucl. Soc., 72, 198-199 (1995).
	B. L. Broadhead and C. M. Hopper, "Updated Tool for Nuclear Criticality Accident Emergency Response,"  1995 Annual Meeting American Nuclear Society, June 25-29, 2005, Philadelphia, Pennsylvania. Trans. Am. Nucl. Soc., 72, 218-220 (1995).
	C. M. Hopper,  "Criticality Safety Considerations for Low-Level-Waste Facilities," 1995 Annual Meeting American Nuclear Society, June 25-29, 2005, Philadelphia, Pennsylvania. Trans. Am. Nucl. Soc., 72,  184-85, (1995).
	B. L. Broadhead, M. D. DeHart, J. C. Ryman, J. S. Tang, and C. V. Parks, Investigation of Nuclide Importance to Functional Requirements Related to Transport and Long-Term Storage of LWR Spent Fuel, ORNL/TM-12742, Lockheed Martin Energy Systems, Inc., Oak Ridge National Laboratory, June 1995.
	E. C. Beahm, C. F. Weber, J. L. Collins, B. Z. Egan, and C. W. Chase, "Washing and Dissolution of Melton Valley Storage Tank Sludge at Oak Ridge National Laboratory," 2nd International Conference on Waste Management, May 17-19, 1995, Washington, D.C.
	L. C. Leal, W. C. Jordan, and R. Q. Wright,  "Nuclear Data for Criticality Safety - Current Issues,"  Proc. Nuclear Criticality Technology and Safety Project Embedded Topical Meeting, May 17, 1995, San Diego, California.
	D. F. Hollenbach and L. M. Petrie, "Assurances Associated with Monte Carlo Code Results," Proc. Nuclear Criticality Technology and Safety Project Embedded Topical Meeting, May 17, 1995, San Diego, California.
	B. L. Broadhead, J. S. Tang, R. L. Childs, C. V. Parks, and H. Taniuchi, "Evaluation of Shielding Analysis Methods in Spent Fuel Cask Environments," EPRI TR-104329, Electric Power Research Institute, May 1995.
	L. C. Leal, O. W. Hermann, and C. V. Parks,  "ARP: A PC-Compatible Scheme for Generating ORIGEN-S Cross- Section Library," Proc. Sixth Annual Inter. Conf. on High-Level Waste Management, April 30 - May 5, 1995, Las Vegas, Nevada.
	L. C. Leal, O. W. Hermann, and C. V. Parks,  "Automatic Rapid Processing Cross-Section Libraries for the Prediction of PWR Spent Fuel Isotopic Compositions,"  Proc. of Inter. Conf. on Math. and Comp., Reactor Physics, and Environmental Analyses, April 30 - May 4, 1995, Portland, Oregon.
	S. M. Bowman, M. D. DeHart, and C. V. Parks, "Validation of SCALE-4 for Burnup Credit Applications," Nucl. Tech., 110,  53 (1995).
	B. L. Broadhead, "Feasibility Assessment of Burnup Credit in the Criticality Analysis of Shipping Casks with Boiling Water Reactor Spent Fuel," Nucl. Tech., 110, 1-21 (1995).
	M. D. DeHart,  SCALE-4 Analysis of Pressurized Water Reactor Critical Configurations: Volume 4 - Three Mile Island Unit 1 Cycle 5, ORNL/TM-12294/V4, Martin Marietta Energy Systems, Oak Ridge National Laboratory, March 1995.
	S. M. Bowman and O. W. Hermann, SCALE-4 Analysis of Pressurized Water Reactor Critical Configurations: Volume 3 - Surry Unit 1 Cycle 2, ORNL/TM-12294/V3, Martin Marietta Energy Systems, Oak Ridge National Laboratory, March 1995.
	S. M. Bowman, O. W. Hermann, and M. C. Brady, SCALE-4 Analysis of Pressurized Water Reactor Critical Configurations: Volume 2 - Sequoyah Unit 2 Cycle 3, ORNL/TM-12294/V2, Martin Marietta Energy Systems, Oak Ridge National Laboratory, March 1995.
	M. D. DeHart, SCALE-4 Analysis of Pressurized Water Reactor Critical Configurations: Volume 1 - Summary, ORNL/TM-12294/V1, Martin Marietta Energy Systems, Oak Ridge National Laboratory, March 1995.
	C. M. Hopper, R. H. Odegaarden, C. V. Parks, and P. B. Fox, Criticality Safety Criteria for License Review of Low-Level Waste Facilities, NUREG/CR-6284 (ORNL/TM-12845), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, March 1995.
	E. C. Beahm, C. F. Weber, J. L. Collins, B. Z. Egan, and C. W. Chase, "Washing and Dissolution of Melton Valley Storage Tank Sludge at Oak Ridge National Laboratory," Efficient Separations and Processing Integrated Program Technical Integration and Exchange Meeting, January 24-26, 1995, Washington, D.C.