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Author(s) / Report
Title / Publication Number / Date |
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S. M. Bowman, M. D. DeHart, and L. M. Petrie, "Integrated KENO Monte Carlo Transport for 3-D Depletion with SCALE," in The Monte Carlo Method: Versatility Unbounded in a Dynamic Computing World, Chattanooga, TN, April 17-21, 2005. |
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S. M. Bowman and J. E. Horwedel, "GeeWiz: Integrated User Interface for SCALE," Trans. Am. Nucl. Soc. 92, 767-769 (2005). |
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S. M. Bowman, B. T. Rearden, and J. E. Horwedel, “Integrated Interactive Visualization for KENO,” in The Monte Carlo Method: Versatility Unbounded in a Dynamic Computing World, Chattanooga, TN, April 17-21, 2005. |
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S. M. Bowman, B. T. Rearden, and J. E. Horwedel, “Complete User Visualization Interface for KENO,” presented at the 2005 NCSD Topical Meeting, Knoxville, TN, September 19-22, 2005. |
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B. L. Broadhead, M. L. Williams, and J. J. Wagschal, "Generalized Linear Least-Squares Adjustment, Revisited," in Proceedings of the Twelfth International Symposium on Reactor Dosimetry, Gatlinburg, TN, May 8-13, 2005. |
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S. N. Cramer, “Bounded Next-Event Estimation and Monte Carlo Forward-Adjoint Correlated Coupling,” Nucl. Sci. Eng. 149(3), 247-258 (March 2005). |
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H. L. Dodds, C. M. Hopper, R. E. Pevey, D. A. Reed, R. G. Taylor, and R. M. Westfall, "Nuclear Criticality Safety Education and Training: Anytime and Anywhere," presented at the 2005 NCSD Topical Meeting, Knoxville, TN, September 19-22, 2005. |
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M. D. DeHart and L. M. Petrie, "Integrated KENO V.a Monte Carlo Transport for
Multidimensional Depletion Within SCALE," presented at the 2004 American Nuclear Society Winter Meeting, Washington, D.C., November 14-18, 2004; Trans. Am. Nucl. Soc. 91, 667-669 (November 2004). |
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M. E. Dunn, N. M. Greene, and L. M. Petrie, "Status of ORNL Cross-Section Processing and Library Generation Capabilities," presented at the International Workshop on Nuclear Data for Generation IV Nuclear Energy Systems, Antwerp, Belgium, April 5-7, 2005. |
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M. E. Dunn, P. B. Fox, N. M. Greene, and L. M. Petrie, "ENDF/B-VI Library Generation and Testing for the SCALE Code System," Trans. Am. Nucl. Soc. 92, 758-759 (2005). |
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M. E. Dunn, D. F. Hollenbach, and L. M. Petrie, "Monte Carlo Methods Development for a Continuous-Energy Version of KENO," in The Monte Carlo Method: Versatility Unbounded in a Dynamic Computing World, Chattanooga, TN, April 17-21, 2005. |
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M. B. Emmett and J. C. Wagner, “MONACO: A New 3-D Monte Carlo Shielding Code for SCALE,” presented at the 2004 American Nuclear Society Winter Meeting, Washington, D.C., November 14-18, 2004; Trans. Am. Nucl. Soc. 91, 701-703 (November 2004). |
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P. B. Fox, L. M. Petrie, Jr., and C. M. Hopper, Minimum Critical Values Study, ORNL/TM-2003/211, Oak Ridge National Laboratory, Oak Ridge, Tenn., July 2005. |
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P. B. Fox and D. F. Hollenbach, KENO-VI Validation, ORNL/TM-2004/60, Oak Ridge National Laboratory, Oak Ridge, Tenn., May 2005. |
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I. C. Gauld and D. E. Mueller, Evaluation of Cross-Section Sensitivities in Computing Burnup Credit Fission Product Concentrations, ORNL/TM-2005/48, Oak Ridge National Laboratory, Oak Ridge, Tenn., August 2005. |
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S. Goluoglu and C. M. Hopper, "Application of Validation Methodologies for a Generic Validation Problem," presented at the 2005 NCSD Topical Meeting, Knoxville, TN, September 19-22, 2005. |
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S. Goluoglu and C. M. Hopper, “Impact of Benchmarks on Potential MOX Throughput,” presented at the 2004 American Nuclear Society Winter Meeting, Washington, D.C., November 14-18, 2004; Trans. Am. Nucl. Soc. 91, 585-587 (November 2004). |
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D. F. Hollenbach and M. E. Dunn, "Status and Preliminary Testing of Continuous-Energy KENO V.a and KENO-VI," presented at the 2005 NCSD Topical Meeting, Knoxville, TN, September 19-22, 2005. |
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D. F. Hollenbach and P. B. Fox, "Benchmark Analysis of the SCALE 5 Versions of the KENO-VI and CENTRM Codes," presented at the 2005 NCSD Topical Meeting, Knoxville, TN, September 19-22, 2005. |
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D. F. Hollenbach and P. B. Fox, CENTRM Validation, ORNL/TM-2004/66, Oak Ridge National Laboratory, Oak Ridge, Tenn., May 2005. |
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D. F. Hollenbach and M. E. Dunn, "Continuous-Energy Version of the SCALE Control Modules for Use with Continuous-Energy KENO V.a and KENO-VI," Trans. Am. Nucl. Soc. 92, 749-750 (2005). |
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C. Hopper, “Guide for Nuclear Criticality Safety in the Storage of Fissile Materials,” presented at the 2004 American Nuclear Society Winter Meeting, Washington, D.C., November 14-18, 2004; Trans. Am. Nucl. Soc. 91, 642-643 (November 2004). |
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D. Loaiza, R. Sanchez, K. Chesson, M. Westfall, and C. Hopper, "Critical Mass Experiment with Niobium - 1 wt% Zirconium Fueled with Highly Enriched Uranium in Support of Project Prometheus," Trans. Am. Nucl. Soc. 92, 580-581 (2005). |
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G. T. Mays, A. L. Qualls, R. L. Lipinski, S. A. Wright, H. S. Bailey, J. A. Bucholz, J. O. Johnson, G. F. Flanagan, R. B. Vilim, C. B. Reed, B. G. Schnitzler, T. J. Hill, D. I. Poston, and R. J. Kapernick, Surface Fission Power for Moon and Mars – Designing for A Mars Human Mission and Adapting for An Early Lunar Robotic Mission (Official Use Only and Applied Technology), ORNL/TM-2005/28, UT-Battelle, LLC, Oak Ridge National Laboratory, July 2005. |
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D. E. Mueller and B. T. Rearden, "Sensitivity Coefficient Generation for a Burnup Credit Cask Model using TSUNAMI-3D," presented at the 2005 NCSD Topical Meeting, Knoxville, TN, September 19-22, 2005. |
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D. E. Mueller and J. C. Wagner, "Application of Sensitivity/Uncertainty Methods to Burnup Credit Criticality Validation," Proceedings of the IAEA Technical Meeting on Advances in Applications of Burnup Credit to Enhance Spent Fuel Transportation, Storage, Reprocessing and Disposition, August 29-September 2, 2005, London, U.K., IAEA-TECDOC-1547, ISBN 92-0-103307-9, Date of Issue:
June 21, 2007. |
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S. E. Parkey, K. R. Elam, and C. F. Weber, "Comparison of Uranyl Nitrate Solution Modeling Methods," presented at the 2005 NCSD Topical Meeting, Knoxville, TN, September 19-22, 2005. |
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C. V. Parks and J. C. Wagner, "A Coordinated U.S. Program to Address Full Burnup Credit in Transport and Storage Casks," Proceedings of the IAEA Technical Meeting on Advances in Applications of Burnup Credit to Enhance Spent Fuel Transportation, Storage, Reprocessing and Disposition, August 29-September 2, 2005, London, U.K., IAEA-TECDOC-1547, ISBN 92-0-103307-9, Date of Issue:
June 21, 2007. |
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C. V. Parks, C. J. Withee, and J. C. Wagner, "U.S. Regulatory Recommendations for Actinide-Only Burnup Credit in Transport and Storage Casks," Proceedings of the IAEA Technical Meeting on Advances in Applications of Burnup Credit to Enhance Spent Fuel Transportation, Storage, Reprocessing and Disposition, August 29-September 2, 2005, London, U.K., IAEA-TECDOC-1547, ISBN 92-0-103307-9, Date of Issue:
June 21, 2007. |
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B. T. Rearden, W. J. Anderson, and G. A. Harms , “Use of Sensitivity and Uncertainty Analysis in the Design of Reactor Physics and Criticality Benchmark Experiments for Advanced Nuclear Fuel,” Nucl. Technol. 151, 133-158 (August 2005). |
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B. T. Rearden, "Improvements in KENO V.a to Support TSUNAMI-3D Sensitivity Calculations," in The Monte Carlo Method: Versatility Unbounded in a Dynamic Computing World, Chattanooga, TN, April 17-21, 2005. |
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B. T. Rearden, C. M. Hopper, and K. R. Elam, "TSUNAMI Analysis of the Applicability of Proposed Experiments to Reactor-Grade and Weapons-Grade Mixed-Oxide Systems," presented at the International Symposium NUCEF2005, Tokai, Japan, February 9-10, 2005. |
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B. T. Rearden, M. L. Williams, and J. E. Horwedel, "Advances in the TSUNAMI Sensitivity and Uncertainty Analysis Codes Beyond SCALE 5," Trans. Am. Nucl. Soc. 92, 760-762 (2005). |
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B. T. Rearden, M. L. Williams, and J. E. Horwedel, "Advances in the TSUNAMI Sensitivity and Uncertainty Analysis Codes Beyond SCALE 5," Trans. Am. Nucl. Soc. 92, 760-762 (2005). |
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I. Remec, T. A. Gabriel, M. Wendel, D. Conner, T. Burgess, R. M. Ronningen, G. Blideanu, G. Bollen, J. Boles, S. Reyes, and L. Ahle, “Particle and Radiation Simulations for the Proposed Rare-Isotope Accelerator Facility,” in Proc. of AccApp05 (Elsevier Science), Venice, Italy, August 29–September 1, 2005.
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C. O. Slater and R. T. Primm III, Calculation of RABBIT and Simulator Worth in the HFIR Hydraulic Tube and Comparison with Measured Values, ORNL/TM-2005/94, UT-Battelle, LLC, Oak Ridge National Laboratory, September 2005. |
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C. O. Slater, D. L. Selby, J. A. Bucholz, J. L. Robertson, and M. L. Crow, “Shielding Calculations for the Upgrade of the HFIR HB2 Beam Line,” Proceedings of the Twelfth International Symposium on Reactor Dosimetry, Gatlinburg, Tenn., May 8-13, 2005. |
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H. P. Smith, and J. C. Wagner, “A Case Study in Manual and Automated Monte Carlo Variance Reduction with a Deep Penetration Reactor Shielding Problem,” Nucl. Sci. Eng. 149, 23-37 (2005). |
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J. T. Thomas, R. M. Westfall, and C. M. Hopper, "History of the Oak Ridge Critical Experiments Program," Trans. Am. Nucl. Soc. 92, 470-471 (2005). |
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J. C. Wagner and D. E. Mueller, "Updated Evaluation of Burnup Credit for Accommodating PWR Spent Nuclear Fuel in High-Capacity Cask Designs," presented at the 2005 NCSD Topical Meeting, Knoxville, TN, September 19-22, 2005. |
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J. C. Wagner and D. E. Mueller, "Assessment of Benefits for Extending Burnup Credit in Transporting PWR Spent Nuclear Fuel in the USA," Proceedings of the IAEA Technical Meeting on Advances in Applications of Burnup Credit to Enhance Spent Fuel Transportation, Storage, Reprocessing and Disposition, August 29-September 2, 2005, London, U.K., IAEA-TECDOC-1547, ISBN 92-0-103307-9, Date of Issue:
June 21, 2007. |
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M. L. Williams, S. Goluoglu, and L. M. Petrie, "Recent Enhancements to the SCALE 5 Resonance Self-Shielding Methodology," Trans. Am. Nucl. Soc. 92, 751-753 (2005). |
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Z. Zhong, T. J. Downar, M. D. DeHart, and M. L. Williams, "Continuous-Energy Multidimensional SN Transport for Problem-Dependent Resonance Self-Shielding Calculations," Trans. Am. Nucl. Soc. 92, 754-757 (2005). |
