2005 Publications
Author(s) / Report Title / Publication Number / Date
S. M. Bowman and J. E. Horwedel, "GeeWiz: Integrated User Interface for SCALE," Trans. Am. Nucl. Soc. 92, 767-769 (2005).
K. T. Clarno, M. L. Williams, J. C. Gehin, C. Cotton, D. Lee, and T. Downar, "Code-to-Code Benchmark of Coolant Void Reactivity (CVR) in the ACR-700 Reactor," Trans. Am. Nucl. Soc. 93, 372-375 (2005).
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).
S. Goluoglu and M. L. Williams, "Modeling Doubly Heterogeneous Systems in SCALE," Trans. Am. Nucl. Soc. 93, 963-965 (2005).
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).
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).
D. E. Mueller and G. A. Harms, "Using the SCALE 5 TSUNAMI-3D Sequence in Critical Experiment Design," Trans. Am. Nucl. Soc. 93, 263-266 (2005).
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).
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).
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).
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).
J. J. Wagschal and C. M. Hopper, "Determination of Consistent Benchmarks Used for Nuclear Criticality Safety Analysis Applications," Trans. Am. Nucl. Soc. 93, 257-259 (2005).
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).
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).
S. M. Bowman, B. T. Rearden, and J. E. Horwedel, “Complete User Visualization Interface for KENO,” 2005 NCSD Topical Meeting, Knoxville, Tenn., September 19-22, 2005.
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," 2005 NCSD Topical Meeting, Knoxville, Tenn., September 19-22, 2005.
J. C. Wagner and D. E. Mueller, "Updated Evaluation of Burnup Credit for Accommodating PWR Spent Nuclear Fuel in High-Capacity Cask Designs," 2005 NCSD Topical Meeting, Knoxville, Tenn., September 19-22, 2005.
S. Goluoglu and C. M. Hopper, "Application of Validation Methodologies for a Generic Validation Problem," 2005 NCSD Topical Meeting, Knoxville, Tenn., September 19-22, 2005.
D. F. Hollenbach and M. E. Dunn, "Status and Preliminary Testing of Continuous-Energy KENO V.a and KENO-VI," 2005 NCSD Topical Meeting, Knoxville, Tenn., September 19-22, 2005.
D. F. Hollenbach and P. B. Fox, "Benchmark Analysis of the SCALE 5 Versions of the KENO-VI and CENTRM Codes," 2005 NCSD Topical Meeting, Knoxville, Tenn., September 19-22, 2005.
D. E. Mueller and B. T. Rearden, "Sensitivity Coefficient Generation for a Burnup Credit Cask Model using TSUNAMI-3D," 2005 NCSD Topical Meeting, Knoxville, Tenn., September 19-22, 2005.
S. E. Parkey, K. R. Elam, and C. F. Weber, "Comparison of Uranyl Nitrate Solution Modeling Methods," 2005 NCSD Topical Meeting, Knoxville, Tenn., September 19-22, 2005.
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, Oak Ridge, Tenn., September 2005.
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).
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.
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,” Proc. of AccApp05 (Elsevier Science), Venice, Italy, August 29–September 1, 2005.
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.
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, Oak Ridge, Tenn., July 2005.
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, London, U.K., August 29-September 2, 2005, IAEA-TECDOC-1547, ISBN 92-0-103307-9, Date of Issue: June 21, 2007.
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, London, U.K., August 29-September 2, 2005, IAEA-TECDOC-1547, ISBN 92-0-103307-9, Date of Issue: June 21, 2007.
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, London, U.K., August 29-September 2, 2005, IAEA-TECDOC-1547, ISBN 92-0-103307-9, Date of Issue: June 21, 2007.
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, London, U.K., August 29-September 2, 2005, IAEA-TECDOC-1547, ISBN 92-0-103307-9, Date of Issue: June 21, 2007.
D. F. Hollenbach and P. B. Fox, CENTRM Validation, ORNL/TM-2004/66, Oak Ridge National Laboratory, May 2005, Oak Ridge, Tenn.
P. B. Fox and D. F. Hollenbach, KENO-VI Validation, ORNL/TM-2004/60, Oak Ridge National Laboratory, May 2005, Oak Ridge, Tenn.
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,” Proc. of the Twelfth International Symposium on Reactor Dosimetry, Gatlinburg, Tenn., May 8-13, 2005.
B. L. Broadhead, M. L. Williams, and J. J. Wagschal, "Generalized Linear Least-Squares Adjustment, Revisited," in Proc. of the Twelfth International Symposium on Reactor Dosimetry, Gatlinburg, Tenn., May 8-13, 2005.
S. M. Bowman, M. D. DeHart, and L. M. Petrie, "Integrated KENO Monte Carlo Transport for 3-D Depletion with SCALE," The Monte Carlo Method: Versatility Unbounded in a Dynamic Computing World, Chattanooga, Tenn., April 17-21, 2005.
S. M. Bowman, B. T. Rearden, and J. E. Horwedel, “Integrated Interactive Visualization for KENO,” The Monte Carlo Method: Versatility Unbounded in a Dynamic Computing World, Chattanooga, Tenn., April 17-21, 2005.
M. E. Dunn, D. F. Hollenbach, and L. M. Petrie, "Monte Carlo Methods Development for a Continuous-Energy Version of KENO," The Monte Carlo Method: Versatility Unbounded in a Dynamic Computing World, Chattanooga, Tenn., April 17-21, 2005.
B. T. Rearden, "Improvements in KENO V.a to Support TSUNAMI-3D Sensitivity Calculations," The Monte Carlo Method: Versatility Unbounded in a Dynamic Computing World, Chattanooga, Tenn., April 17-21, 2005.
M. E. Dunn, N. M. Greene, and L. M. Petrie, "Status of ORNL Cross-Section Processing and Library Generation Capabilities," International Workshop on Nuclear Data for Generation IV Nuclear Energy Systems, Antwerp, Belgium, April 5-7, 2005.
S. N. Cramer, “Bounded Next-Event Estimation and Monte Carlo Forward-Adjoint Correlated Coupling,” Nucl. Sci. Eng. 149(3), 247-258 (March 2005).
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," International Symposium NUCEF2005, Tokai, Japan, February 9-10, 2005.
