Oak Ridge National Laboratory

Nuclear Modeling, Design, and Safety
2009 Publications

Author(s) / Report Title / Publication Number / Date
B. B. Bevard, J. C. Wagner, C. V. Parks, and M. Aissa, Review of Information for Spent Nuclear Fuel Burnup Confirmation, NUREG/CR-6998, prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., December 2009.
D. E. Holcomb, S. M. Cetiner, G. F. Flanagan, F. J. Peretz, and G. L. Yoder, Jr., An Analysis of Testing Requirements for Fluoride Salt-Cooled High Temperature Reactor Components, ORNL/TM-2009/297, Oak Ridge National Laboratory, Oak Ridge, Tenn., November 2009.
H. Akkurt, K. Bekar, and K. F. Eckerman, "Assessment of Organ Doses for a Glovebox Worker Using Realistic Postures with PIMAL and VOXMAT," Trans. Am. Nucl. Soc. 101, 671-673 (2009).
K. B. Bekar and T. M. Evans, "MCNP-BRL: A Linkage Between MCNP and CAD Geometry," Trans. Am. Nucl. Soc. 101, 623-526 (2009).
J. J. Carbajo and L. Qualls, "Effect of Control Systems on Space Reactor Transients," Trans. Am. Nucl. Soc. 101, 320-321 (2009).
M. D. DeHart and A. P. Ulses, "A Proposed Code-to-Code Benchmark for the Depletion of HTGR Fuel," Trans. Am. Nucl. Soc. 101, 773-775 (2009).
M. D. DeHart, S. Goluoglu, and J. Leppanen, "A Comparison of Deterministic and Monte Carlo Depletion Methods for HTGR Fuel Elements," Trans. Am. Nucl. Soc. 101, 778-781 (2009).
G. Ilas and I. C. Gauld, "SCALE 6 Analysis of Isotopic Assay Benchmarks for PWR Spent Fuel" Trans. Am. Nucl. Soc. 101, 691-693 (2009).
I. C. Gauld and Y. Rugama, "Experiment Isotopic Data Compiled by the OECD/NEA EGADSNF" Trans. Am. Nucl. Soc. 101, 685-687 (2009).
J. Leppanen and M. DeHart, "HTGR Reactor Physics and Burnup Calculations Using the Serpent Monte Carlo Code" Trans. Am. Nucl. Soc. 101, 782-784 (2009).
G. T. Mays, W. C. Jochem, S. R. Greene, R. J. Belles, M. S. Cetiner, and S. W. Hadley, "Identifying and Characterizing Candidate Areas for Siting New Nuclear Capacity in the United States," Trans. Am. Nucl. Soc. 101, 505-507 (2009).
D. E. Mueller and B. T. Rearden, "SCALE TSUNAMI Analysis of Critical Experiments for Validation of 233U Systems," Trans. Am. Nucl. Soc. 101, 455-459 (2009).
W. R. Hix, M. L. Baird, E. J. Lentz, C.-T. Lee, B. Messer, A. Mezzacappa, J. M. Blondin, S. W. Bruenn, and P. Marronetti, "Understanding Core-Collapse Supernovae," Proc. 76th Annual Meeting of the Southeastern Section of the American Physical Society, Atlanta, GA, November 11, 2009.
J. M. Scaglione and J. C. Wagner, Burnup Credit Approach for the Proposed United States Repository at Yucca Mountain, Proc. IAEA/CSN International Workshop on Advances in Applications of Burnup Credit for Spent Fuel Storage, Transport, Reprocessing, and Disposition, Cordoba, Spain, October 2730, 2009.
J. Turner, K. Clarno, G. Hansen, Roadmap to an Engineering-SCALE Nuclear Fuel Performance and Safety Code, ORNL/TM-2009/233, Oak Ridge National Laboratory, Oak Ridge, Tenn., September 2009.
T. M. Evans and K. T. Clarno, C++ Coding Standards for the AMP Project, ORNL/TM-2009/240, Oak Ridge National Laboratory, Oak Ridge, Tenn., September 2009.
R. Kisner, D. Holcomb, J. Mullens, T. Wilson, R. Wood, K. Korsah, M. Muhlheim, A. Qualls, M. Howlader, G. Wetherington, Jr., P. Chiaro, Jr., and A. Loebl, Design Practices for Communications and Workstations in Highly Integrated Control Rooms, NUREG/CR-6991 (ORNL/TM-2007/184), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., September 2009.
K. H. Guber, "High-Resolution Neutron Cross-Section Measurements at ORELA," Proc. Nuclear Data Measurements, Theory and Applications, Budapest, Hungary, September 23-25, 2009.
G. Radulescu and I. C. Gauld, "Enhancements to the Burnup Credit Criticality Safety Analysis Sequence in SCALE," Proc. 2009 Nuclear Criticality Safety Division Topical Meeting on Realism, Robustness and the Nuclear Renaissance, NCSD 2009, Richland, WA, September 13-17, 2009.
B. T. Rearden, R. A. Lefebvre, A. B. Thompson, Y. Rugama, N. Soppera, and M. Bossant, "The VIBE Tool of SCALE Validation, Interpretation, and Bias Estimation," Proc. 2009 Nuclear Criticality Safety Division Topical Meeting on Realism, Robustness and the Nuclear Renaissance, NCSD 2009, Richland, WA, September 13-17, 2009.
B. T. Rearden, I. Duhamel, and E. Letang, "New SCALE Sensitivity/Uncertainty Capabilities Applied to Bias Estimation and to Design of MIRTE Reference Experiments," Proc. 2009 Nuclear Criticality Safety Division Topical Meeting on Realism, Robustness and the Nuclear Renaissance, NCSD 2009, Richland, WA, September 13-17, 2009.
D. J. Spellman, B. B. Bevard, J. B. Chesser, L. J. Ott, and R. N. Morris, "Development of Commercial-Length Nuclear Fuel Post-Irradiation Examination Capabilities at the Oak Ridge National Laboratory," presented at GLOBAL 2009, The Nuclear Fuel Cycle, Paris, France, September 6-11, 2009.
L. J. Ott, B. B. Bevard, R. J. Ellis, J. L. McDuffee, and D. J. Spellman, "Advanced Fuel/Cladding Testing Capabilities in the ORNL High Flux Isotope Reactor," presented at GLOBAL 2009, The Nuclear Fuel Cycle, Paris, France, September 6-11, 2009.
B. B. Bevard, T.-L. Sham, J. G. Merkle, L. J. Ott, and D. J. Spellman, "An Expanding Plug Test Method for Determining Hoop Stress-Strain Curves of Irradiated Nuclear Fuel Cladding," presented at GLOBAL 2009, The Nuclear Fuel Cycle, Paris, France, September 6-11, 2009.
K. Williams, "'Top-Down' Life-Cycle Costing for Nuclear Processes and Facilities," presented at GLOBAL 2009, The Nuclear Fuel Cycle, Paris, France, September 6-11, 2009.
K. Williams and D. Shropshire, "Economic Analysis of Symbiotic Light-Water-Reactor/Fast-Burner-Reactor Fuel Cycles Proposed as Part of the U.S. Advanced Fuel Cycle Initiative (AFCI)," presented at GLOBAL 2009, The Nuclear Fuel Cycle, Paris, France, September 6-11, 2009.
B. L. Kirk, "The Radiation Safety Information Computational Center (RSICC) - A Resource for Computational Tools for Nuclear Applications," Proc. Institute of Nuclear Materials Management 50th Annual Meeting, Tuscon, AZ, July 12-16, 2009.
J. J. Carbajo, "The Flow Model on the Containment Pressure After a Feedwater Line Break," Trans. Am. Nucl. Soc. 100, 455-456 (2009).
SCALE:  A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluations, ORNL/TM-2005/39, Version 6 , Vols. I–III, January 2009.  Available from Radiation Safety Information Computational Center at Oak Ridge National Laboratory as CCC-750.
L. R. Baylor, S. K. Combs, C. R. Foust, T. C. Jernigan, S. J. Meitner, P. B. Parks, J. B. Caughman, S. Maruyama, A. L. Qualls, D. A. Rasmussen, C. E. Thomas, "Pellet Fueling, ELM Pacing, and Disruption Mitigation Technology Development for ITER," Proc. 22nd IAEA Fusion Energy Conference, Geneva, Switzerland, October 13-18, 2008 (published January 2009).
B. T. Rearden, D. Mueller, S. M. Bowman, R. D. Busch, and S. Emerson, TSUNAMI Primer:  A Primer for Sensitivity/Uncertainty Calculations with SCALE, ORNL/TM-2009/027, Oak Ridge National Laboratory, Oak Ridge, Tenn., January 2009.
S. M. Bowman, SCALE Newsletter, Vol. 39, January 2009.


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