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1996-99 Publications


B. T. Rearden, "Development of SAMS: A Three-Dimensional Sensitivity Analysis Module for the SCALE Code System," Ph.D. Dissertation, Texas A&M University, December 1999, College Station, Tex.

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, Long Beach, Calif., November 14-18, 1999, 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, Long Beach, Calif., November 14-18, 1999, 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, Long Beach, Calif., November 14-18, 1999, 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, Long Beach, Calif., November 14-18, 1999, 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, Long Beach, Calif., November 14-18, 1999, 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, Long Beach, Calif., November 14-18, 1999, 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, Long Beach, Calif., November 14-18, 1999, Trans. Am. Nucl. Soc. 81, 170-171, 1999.

M. B. Emmett, "MORSE: Present Capabilities and Future Directions," Proceedings IRRMA'99 Meeting, 4th Topical Meeting on Industrial Radiation and Radioisotope Measurement Applications, Raleigh, N.C., October 3-7, 1999. [Abstract]

M. D. DeHart, "A Deterministic Study of the Deficiency of the Wigner-Seitz Approximation for Pu/MOX Fuel Pins," Proceedings M&C'99-Madrid, Mathematics and Computations Meeting, Madrid, Spain, September 27-30, 1999.

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, Palais des Congres, Versailles, France, September 20-24, 1999.

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, Palais des Congres, Versailles, France, September 20-24, 1999.

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, Palais des Congres, Versailles, France, September 20-24, 1999.

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, Palais des Congres, Versailles, France, September 20-24, 1999.

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, Palais des Congres, Versailles, France, September 20-24, 1999.

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, Palais des Congres, Versailles, France, September 20-24, 1999.

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, Palais des Congres, Versailles, France, September 20-24, 1999.

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, Palais des Congres, Versailles, France, September 20-24, 1999.

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 et al., 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. 28(11), 1207-1238, (1999).

1998

C. M. Hopper, Candidate Methodologies for Criticality Safety LLW Emplacement Guidance, ORNL/M-6617, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, November 1998.

N. M. Greene, Prototypic Testing of Codes to Process All Scattering and Production Reactions and Produce Multigroup Cross-Section Libraries, ORNL/M-6620, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, November 1998.

M. C. Brady et al., "International Studies on Burnup Credit Criticality Safety and an OECD/NEA Working Group," Vol. 1, pp. 624-630 in Proceedings of International Conference on the Physics of Nuclear Science and Technology, Long Island, N.Y., October 5-8, 1998.

B. D. Murphy, Prediction of the Isotopic Composition of UO2 Fuel from a BWR Analysis of the DU1 Sample from the Dodewaard Reactor, ORNL/TM-13687, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, October 1998.

M. E. Dunn, Production of MCNP Cross Sections Using the AMPX and NJOY Processing Code Systems, ORNL/TM-6609, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, October 1998.

E. C. Beahm, C. F. Weber, and T. A. Dillow, Technical Assistance in Review of Source Term Related Issues of Advanced Reactors, NUREG/CR-6408 (ORNL/TM-13144), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, October 1998.

O. W. Hermann, P. R. Daniel, and J. C. Ryman, ORIGEN-S Decay Data Library and Half-Life Uncertainties, ORNL/TM-13624, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, September 1998.

O. W. Hermann and M. D. DeHart, Validation of SCALE (SAS2H) Isotopic Predictions for BWR Spent Fuel, ORNL/TM-13315, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, September 1998.

R. D. Dabbs, B. L. Broadhead, and B. T. Fowler, "Reporting Actinide Inventories in Irradiated Fuel at the High Flux Isotope Reactor," Vol. 2, pp. 581-588 (Session 20) in Proc. of Third Topical Meeting on DOE Spent Nuclear Fuel and Fissile Materials Management, Charleston, S.C., September 8-11, 1998.

J. J. Lichtenwalter and C. V. Parks, "Bounding Criticality Safety Analyses for Shipments of Unconfigured Spent Nuclear Fuel," Vol. 1, pp. 112-117 (Session 4) in Proc. of Third Topical Meeting on DOE Spent Nuclear Fuel and Fissile Materials Management, Charleston, S.C., September 8-11, 1998.

B. L. Broadhead, K-Infinite Trends with Burnup, Enrichment, and Cooling Time for BWR Fuel Assemblies, ORNL/M-6155, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, August 1998.

B. L. Broadhead and B. T. Rearden, Exploratory Studies for Three-Dimensional Sensitivity Methods, ORNL/M-6583, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, August 1998.

C. V. Parks et al., "Development of Nuclear Analysis Capabilities for DOE Waste Management Activities," CONF-980736, pp. 222-223, in Proceedings of Environmental Management Science Program Workshop, Chicago, Ill., July 27-30, 1998.

C. V. Parks, C. M. Hopper, and J. J. Lichtenwalter, Assessment and Recommendations for Fissile-Material Packaging Exemptions and General Licenses Within 10 CFR Part 71, NUREG/CR-5342 (ORNL/TM-13607), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, July 1998.

B. L. Broadhead, H. Taniuchi, and C. V. Parks, "Chapter 9. Shielding," pp. 9-1 - 9-52, in The Radioactive Materials Packaging Handbook Design, Operations, and Maintenance, L. B. Shappert, Ed., ORNL/M-5003, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, June 1998.

C. V. Parks, S. M. Bowman, and B. L. Broadhead, "Appendix E. The Standardized Computer Analysis for Licensing Evaluation (SCALE) Program," pp. E-1 - E-12, in The Radioactive Materials Packaging Handbook Design, Operations, and Maintenance, L. B. Shappert, Ed., ORNL/M-5003, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, June 1998.

C. V. Parks et al., Annual EMSP Summary Progress Report. Project Title: Development of Nuclear Analysis Capabilities for DOE Waste Management Activities, ORNL/M-6549, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, June 1998.

M. D. DeHart, "An Advanced Deterministic Method for Spent-Fuel Criticality Safety Analysis," ANS 1998 Annual Meeting and Embedded Topical Meeting, Nashville, Tenn., June 7-11, 1998, Trans. Am. Nucl. Soc. 78, 170-172 (1998).

D. F. Hollenbach and L. M. Petrie, "Comparison of the CENTRM Resonance Processor to the NITAWL Resonance Processor in SCALE," ANS 1998 Annual Meeting and Embedded Topical Meeting, Nashville, Tenn., June 7-11, 1998, Trans. Am. Nucl. Soc. 78, 158 (1998).

J. J. Lichtenwalter, "Validation of KENO-VI - A Comparison with Hexagonal Lattice LWR Critical Experiments," ANS 1998 Annual Meeting and Embedded Topical Meeting, Nashville, Tenn., June 7-11, 1998, Trans. Am. Nucl. Soc. 78, 156-158 (1998).

C. V. Parks, H. R. Dyer, and G. E. Whitesides, "Chapter 10. Criticality Safety," pp. 10-1 - 10-48, in The Radioactive Materials Packaging Handbook Design, Operations, and Maintenance, L. B. Shappert, Ed., ORNL/M-5003, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, June 1998.

C. V. Parks, H. R. Dyer, and M. D. DeHart, "Appendix C. A Statistical Technique for Determining Subcritical Limits," pp. C-1 - C-8, in The Radioactive Materials Packaging Handbook Design, Operations, and Maintenance, L. B. Shappert, Ed., ORNL/M-5003, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, June 1998.

L. B. Shappert, D. W. Turner, C. V. Parks, and G. A. Aramayo, "Recent Experience in Planning, Packaging and Preparing Noncommercial Spent Fuel for Shipment in the United States," Vol. 4, pp. 1438-1445 in Proceedings of PATRAM 98 The 12th International Conference on the Packaging and Transportation of Radioactive Materials, Paris, France, May 10-15, 1998 (Poster Session).

C. V. Parks et al., "Assessment of the U.S. Regulations for Fissile Exemptions and Fissile Material General Licenses," Vol. 3, pp. 1098-1106 in Proceedings of PATRAM 98 The 12th International Conference on the Packaging and Transportation of Radioactive Materials, Paris, France, May 10-15, 1998.

C. F. Weber, "A Solubility Model for Aqueous Solutions Containing Sodium, Fluoride, and Phosphate," Ph.D. Dissertation, University of Tennessee, May 1998, Knoxville, Tenn.

D. F. Hollenbach and L. M. Petrie, "Assurances Associated with Monte Carlo Code Results," pp. 71-73, Proceedings of the Nuclear Criticality Technology Safety Workshop, San Diego, Calif., May 16-17, 1995, LA-13439-C, April 1998.

C. M. Hopper and B. L. Broadhead, An Updated Nuclear Criticality Slide Rule: Functional Slide Rule, NUREG/CR-6504, Vol. 2 (ORNL/TM-13322/V2), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, April 1998.

L. C. Leal, O. W. Hermann, S. M. Bowman, and C. V. Parks, ARP: Automatic Rapid Process for the Generation of the Problem-Dependent SAS2H/ORIGEN-S Cross-Section Libraries, ORNL/TM-13584, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, April 1998.

B. D. Murphy, Characteristics of Spent Fuel from Plutonium Disposition Reactors, Vol. 4: Westinghouse Pressurized-Water-Reactor Fuel Cycle Without Integral Absorber, ORNL/TM-13170/V4, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, April 1998.

J. C. Ryman and O. W. Hermann, Characteristics of Spent Fuel from Plutonium Disposition Reactors, Vol. 2: A General Electric Boiling-Water-Reactor Design, ORNL/TM-13170/V2, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, April 1998.

B. L. Broadhead, R. L. Childs, C. M. Hopper, and C. V. Parks, "Dose Consequences from a Postulated Criticality Occurring in a Low-Level-Waste Disposal Facility," Vol. 1, pp. I-390 - I-395, in Proceedings of the 1998 ANS Radiation Protection and Shielding Division Topical Conference on Technologies for the New Century, Nashville, Tenn., April 19-23, 1998.

M. B. Emmett, S. M. Bowman, and B. L. Broadhead, "SCALE Radiation Shielding Verification and Validation Package," Vol. 1, pp. I-91 - I-97 in Proceedings of the 1998 ANS Radiation Protection and Shielding Division Topical Conference on Technologies for the New Century, Nashville, Tenn., April 19-23, 1998.

S. M. Bowman and D. L. Barnett, "SINEX: SCALE Shielding Analysis GUI for X-Windows," Vol. 2, pp. II-331 - II-337 in Proceedings of the 1998 ANS Radiation Protection and Shielding Division Topical Conference on Technologies for the New Century, Nashville, Tenn., April 19-23, 1998.

B. L. Broadhead, R. L. Childs, C. M. Hopper, and C. V. Parks, "Dose Consequences from a Postulated Criticality Occurring in a Low-Level-Waste Disposal Facility," Vol. 1, pp. I-390 - I-395 in Proceedings of the 1998 ANS Radiation Protection and Shielding Division Topical Conference on Technologies for the New Century, Nashville, Tenn., April 19-23, 1998.

J. S. Tang, J. K. Mattingly, J. T. Mihalczo, and J. A. McEvers, "Shielding Design for the Source Module of a Fissile Mass-Flow Monitor," Vol. 1, pp. I-84 - I-90 in Proceedings of the 1998 ANS Radiation Protection and Shielding Division Topical Conference on Technologies for the New Century, Nashville, Tenn., April 19-23, 1998.

O. W. Hermann, M. D. DeHart, and B. D. Murphy, Evaluation of Measured LWR Spent Fuel Composition Data for Use in Code Validation End-User Manual, ORNL/M-6121, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, February 1998.

B. D. Murphy, Verification of the LWRARC Code for Light-Water-Reactor Afterheat Rate Calculations, NUREG/CR-6536 (ORNL/TM-13396), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, February 1998.

C. F. Weber, "Convergence of the Equilibrium Code SOLGASMIX," J. Comp. Physics 145, 655-670 (1998).

1997

K. R. Elam, C. W. Forsberg, C. M. Hopper, and R. Q. Wright, Isotopic Dilution Requirements for 233U Criticality Safety in Processing and Disposal Facilities, ORNL/TM-13524, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, November 1997.

R. M. Westfall, "Evolution of Cross-Section Data for Criticality Safety Applications," ANS 1997 Winter Meeting, Albuquerque, N. Mex., November 16-20, 1997, Trans. Am. Nucl. Soc. 77, 229-230 (1997).

C. V. Parks, "Overview of Validation," ANS 1997 Winter Meeting & Embedded Topical Meetings, Albuquerque, N. Mex., November 16-20, 1997.

S. M. Bowman, B. L. Broadhead, D. F. Hollenbach, and L. M. Petrie, Joint Report of Foreign Travel to Rez (near Prague), Czech Republic, October 9-18, 1997, ORNL/FTR-6399, November 1997.

N. M. Greene and R. M. Westfall, "Cross Sections for Criticality Safety Applications," ANS 1997 Winter Meeting, Albuquerque, N. Mex., November 16-20, 1997, Trans. Am. Nucl. Soc. 77, 227-229 (1997).

M. J. Haire, W. C. Jordan, and R. G. Taylor, "Storage Array Reflection Considerations," ANS 1997 Winter Meeting, Albuquerque, N. Mex., November 16-20, 1997, Trans. Am. Nucl. Soc. 77, 222-223 (1997).

B. L. Broadhead, "Application of Generalized Linear Least-Squares Methodology to Criticality Safety Computations," ANS 1997 Winter Meeting, Albuquerque, N. Mex., November 16-20, 1997, Trans. Am. Nucl. Soc. 77, 234-235 (1997).

B. L. Broadhead, R. T. Primm III, and S. E. Fisher, "Strategy for Validating Shielding Methods for Reactor-Based Disposition of Weapons-Grade Plutonium," ANS 1997 Winter Meeting, Albuquerque, N. Mex., November 16-20, 1997, Trans. Am. Nucl. Soc. 77, 318-319 (1997). [Invited]

R. T. Primm III, B. D. Murphy, and J. B. Knauer, Jr., Joint Report of Foreign Travel to SCK*CEN Analytical Laboratory and Belgonucleaire, Brussels, Belgium, October 29-31, 1997, ORNL/FTR-6407, October 1997.

S. Raman, R. L. Walker, J. K. Dickens, and B. D. Murphy, "The US/UK Actinides Experiment at the Dounreay PFR," Vol. 2, pp. 1390-1392 in Proceedings of the International Conference on Future Nuclear Systems: Challenge Towards Second Nuclear Era with Advanced Fuel Cycles, Pacifico Yokohama, Yokohama, Japan, October 5-10, 1997.

D. F. Hollenbach and C. M. Hopper, "Criticality Safety Considerations for MSRE Fuel Drain Tank Uranium Aggregation," pp. 73-79 in Proceedings of the Topical Meeting on Criticality Safety Challenges in the Next Decade, Chelan, Wa., September 7-12, 1997.

C. M. Hopper and C. V. Parks, "Potential for and Consequences of Criticality Resulting from Hydrogeochemically Concentrated Fissile Uranium Blended with Soil in Low-Level Waste Disposal Facilities," pp. 73-79 in Proceedings of the Topical Meeting on Criticality Safety Challenges in the Next Decade, Chelan, Wa., September 7-12, 1997.

C. M. Hopper, R. Q. Wright, K. R. Elam, and C. W. Forsberg, "Isotopic Dilution of U-233 with Depleted Uranium for Criticality Safety in Processing and Disposal," Proceedings of the Topical Meeting on Criticality Safety Challenges in the Next Decade, Chelan, Wa., September 7-12, 1997.

J. J. Lichtenwalter, "Heterogeneous Reactivity Effects in Medium- and High-Enriched Uranium Metal-Water Systems," Proceedings of the Topical Meeting on Criticality Safety Challenges in the Next Decade, Chelan, Wa., September 7-12, 1997.

D. E. Cabrilla and R. M. Westfall, "Meeting the Challenge: Assuring Adequate Criticality Predictability," in pp. 3–8 in Proceedings Criticality Safety Challenges in the Next Decade Topical Meeting of the Nuclear Criticality Safety Division, Chelan, Wa., September 7-12, 1997.

B. D. Murphy, Characteristics of Spent Fuel From Plutonium Disposition Reactors. Vol. 3: A Westinghouse Pressurized-Water Reactor Design, ORNL/TM-13170/V3, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, July 1997.

S. M. Bowman, M. D. DeHart, and C. V. Parks, "USLSTATS: Computerized Statistical Methods for Determination of Bias and Subcritical Limits," ANS 1997 Annual Meeting, Orlando, Fla., June 1-5, 1997, Trans. Am. Nucl. Soc. 76, 238-241, (1997).

L. Petrie, D. K. Parsons, and G. D. Spriggs, "KENO Lifetimes," ANS 1997 Annual Meeting, Orlando, Fla., June 1-5, 1997, Trans. Am. Nucl. Soc. 76, 367-368 (1997).

M. D. DeHart and C. V. Parks, "SCALE Depletion Calculations Based on Two-Dimensional PWR Assembly Flux Solutions," ANS 1997 Annual Meeting, Orlando, Fla., June 1-5, 1997, Trans. Am. Nucl. Soc. 76, 53-57 (1997).

M. E. Dunn et al., "Continuous-Energy Methods Development for the Monte Carlo Code KENO V.a," ANS 1997 Annual Meeting, Orlando, Fla., June 1-5, 1997, Trans. Am. Nucl. Soc. 76, 234-235 (1997).

L. E. Toran et al., The Potential for Criticality Following Disposal of Uranium at Low- Level Waste Facilities. Volume 1: Uranium Blended with Soil, NUREG/CR-6505, Vol. 1 (ORNL/TM-13323/V1), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, June 1997.

H. R. Dyer and C. V. Parks, Recommendations for Preparing the Criticality Safety Evaluation of Transportation Packages, NUREG/CR-5661 (ORNL/TM-11936), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, April 1997.

B. L. Broadhead, C. M. Hopper, R. L. Childs, and J. S. Tang, An Updated Nuclear Criticality Slide Rule. Volume 1: Technical Basis, NUREG/CR-6504, Vol. 1 (ORNL/TM-13322/V1), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, April 1997.

S. M. Bowman, et al., SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation, Vols. I-III, NUREG/CR-0200, Rev. 5 (ORNL/NUREG/CSD-2/R5), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, March 1997.

J. J. Lichtenwalter, S. M. Bowman, and M. D. DeHart, Criticality Benchmark Guide for Light-Water-Reactor Fuel in Transportation and Storage Packages, NUREG/CR-6361 (ORNL/TM-13211), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, March 1997.

B. L. Broadhead et al., "Evaluation of Shielding Analysis Methods in Spent-Fuel Cask Environments," Nucl. Tech. 117, 206-222, February 1997.

R. Raman, R. L. Walker, and B. D. Murphy, "Actinide Behavior in the US/UK Actinides Experiment at the Dounreay PFR," pp. 1326-1328 in Proceedings of the Nuclear Data for Science and Technology, G. Reffo, A. Ventura, and C. Grandi (Eds.), SIF, Bologna, 1997.

1996

B. L. Broadhead, "Shielding Analyses: The Rabbit vs the Turtle," Vol. 1, p. 322 in Proc. of Rad. Prot. & Shielding 1996 Topical Meeting, Advances and Applications in Radiation Protection and Shielding (1996).

B. L. Broadhead and R. L. Childs, "ORNL Contribution to the IAEA Benchmark Problem on Fission Reactor Decommissioning," Vol. 2, p. 541 in Proc. of Rad. Prot. & Shielding 1996 Topical Meeting, Advances and Applications in Radiation Protection and Shielding (1996).

Y. Y. Liu, R. A. Schwarz, and J. S. Tang, "Monte Carlo Simulation of Radiation Streaming from a Radioactive Material Shipping Cask," Vol. 2, p. 1053 in Proc. 1996 Top. Mtg. Radiation Protection & Shielding, Advances and Applications in Radiation Protection and Shielding (1996).

R. L. Childs, "The FALSTF Last-Flight Computer Program," in Proc. of Radiation Protection & Shielding 1996 Topical Meeting, Advances and Applications in Radiation Protection and Shielding (1996).

C. V. Parks et al., "SCAMPI: A Code Package for Cross-Section Processing," Vol. 2, p. 1080 in Proc. Rad. Prot. & Shielding 1996 Topical Meeting, Advances and Applications in Radiation Protection and Shielding (1996).

C. V. Parks and G. E. Whitesides, "Review of the International Conference on Nuclear Criticality - Issues, Discussions, and Challenges," in Proc. of First NUCEF International Symposium, NUCEF'95, Engineering Safety of Nuclear Fuel Cycle Facility, Hitachinaka, Ibaraki, Japan, October 16-17, 1995, JAERI-Conf 96-003, 95-101 (1996).

M. B. Emmett and W. C. Jordan, Guide to Verification and Validation of the SCALE-4 Criticality Safety Software, NUREG/CR-6483 (ORNL/TM-12834), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, December 1996.

B. L. Broadhead, M. B. Emmett, and J. S. Tang, Guide to Verification and Validation of the SCALE-4 Radiation Shielding Software, NUREG/CR-6484 (ORNL/TM-13277), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, December 1996.

B. D. Murphy, T. D. Newton, and S. Raman, Preliminary Calculational Analysis of the Actinide Samples from FP-4 Exposed in the Dounreay Prototype Fast Reactor, ORNL-6889, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, December 1996.

S. M. Bowman and T. Suto, SCALE-4 Analysis of Pressurized Water Reactor Critical Configurations: Volume 5 - North Anna Unit 1 Cycle 5, ORNL/TM-12294/V5, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, October 1996.

C. F. Weber and E. C. Beahm, Chemical Modeling of Waste Sludges, ORNL/TM-13200, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, October 1996.

M. D. DeHart and O. W. Hermann, An Extension of the Validation of SCALE (SAS2H) Isotopic Predictions for PWR Spent Fuel, ORNL/TM-13317, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, September 1996.

D. F. Hollenbach and C. M. Hopper, Criticality Safety Study of the MSRE Auxiliary Charcoal Bed, ORNL/M-5450, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, September 1996.

M. C. Brady et al., "Findings of an International Study on Burnup Credit," Vol. 4, PHYSOR '96 in Proc. International Conf. on Physics of Reactors, September 16-20, 1996, Mito, Japan.

C. F. Weber and B. Z. Egan, "Convergence Analysis of the Equilibrium Code SOLGASMIX," 212th Natl. Mtg. Am. Chem. Soc., Orlando, Fla., August 25-29, 1996.

M. D. DeHart, M. C. Brady, and C. V. Parks, OECD/NEA Burnup Credit Calculational Criticality Benchmark Phase I- B Results, NEA/NSC/DOC(96)-06 (ORNL-6901), Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, June 1996.

L. C. Leal, R. Q. Wright, and J. M. Rammsy, "Self-Shielded Reaction-Rate Calculations for 235U from 0 to 2250 eV," 1996 Annual Meeting American Nuclear Society, Reno, Nev., June 16-20, 1996, Trans. Am. Nucl. Soc. 74, 333-334 (1996).

R. Q. Wright, L. C. Leal, and J. M. Rammsy, "Data Testing of 235U Evaluation," 1996 Annual Meeting American Nuclear Society, Reno, Nev., June 16-20, 1996, Trans. Am. Nucl. Soc. 74, 200-201 (1996).

B. D. Murphy, Characteristics of Spent Fuel from Plutonium Disposition Reactors, Vol. 1: The Combustion Engineering System 80+ Pressurized-Water-Reactor Design, ORNL/TM-13170/V1, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, June 1996.

M. D. DeHart, Sensitivity and Parametric Evaluations of Significant Aspects of Burnup Credit for PWR Spent Fuel Packages, ORNL/TM-12973, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, May 1996.

D. E. Mueller, C. M. Hopper, E. C. Crume, Jr., "Molten Salt Reactor Experiment Remediation," Nuclear Criticality Technology Safety Project, May 14-15, 1996.

R. B. Pope et al., "Benefits and Impacts on the System Elements of the CRWMS of Utilizing Depleted Uranium Silicate Glass as Backfill for Spent Fuel Waste Packages," in 1996 Inter. High Level Radioactive Waste Management Conference, Las Vegas, Nev., April 29-May 3, 1996.

C. W. Forsberg et al., "Depleted-Uranium-Silicate Backfill of Spent Fuel Waste Packages for Improved Repository Performance and Criticality Control," 1996 Inter. High-Level Radioactive Waste Management Conference, Las Vegas, Nev., April 29-May 3, 1996.

S. M. Bowman, "SCALE-PC Shielding Analysis Sequences," Vol. 2, p. 996 in Proc. ANS 1996 Radiation Protection and Shielding Division Topical Meeting, Cape Cod, Mass., April 21-25, 1996.

M. D. DeHart, J. S. Tang, and C. W. Forsberg, "Shielding Analysis of Depleted Uranium Sand Filler Concept for Spent Fuel Cask Designs," ANS 1996 Radiation Protection and Shielding Division Topical Meeting, Cape Cod, Mass., April 21-25, 1996.

M. B. Emmett, Configuration Management Plan for the SCALE Code System, SCALE-CMP-001 (Rev. 5), Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, April 1996.

B. L. Broadhead, R. L. Childs, and C. V. Parks, Shielding and Criticality Analyses of Phase I - Reference Truck and Rail Cask Designs for Spent Nuclear Fuel, ORNL/TM-12395, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, March 1996.

R. L. Childs, The FALSTF Last-Flight Computer Program, ORNL/TM-12675, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, January 1996.

B. L. Broadhead, R. L. Childs, J. S. Tang, and C. M. Hopper, Verification of Criticality Accident Alarm System for Molten Salt Reactor Remediation Activities, ORNL/CF-95/99, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, January 1996.

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