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Author(s) / Report
Title / Publication Number / Date |
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W. J. Anderson, M.
Saglam, B. T. Rearden, and R. Smith,
"Reactor Physics and Criticality Benchmark Evaluations for Advanced Nuclear
Fuel: Experiment Analysis Comparison Report," 09-031.pdf in
Proc. of American Nuclear Society, Advances in Nuclear Fuel Management
III, October 5-8, 2003, Hilton Head Island, South Carolina. |
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J. F. Birdwell, Jr., R. M. Counce, C. O. Slater, R. A. Price, and D. D. Walker, Conceptual Design of a Simplified Skid-Mounted Caustic-Side Solvent Extraction Process for Removal of Cesium from Savannah River Site High-Level Waste, ORNL/TM-2004/59, UT-Battelle, LLC, Oak Ridge National Laboratory, May 2004. |
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E. D. Blakeman, J. A. Bucholz, and R. D. Cheverton, Calculation of dpa Rates at the HFIR Beam Tube HB-2 Beam Tube Nozzle Corner Using Three-Dimensional Discrete Ordinates and Monte Carlo Models, ORNL/TM-2003/213, UT-Battelle, LLC, Oak Ridge National Laboratory, June 2004. |
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S.
M. Bowman, D. F. Hollenbach, M. D. DeHart, B. T. Rearden, I. C. Gauld,
and S. Goluoglu, "SCALE 5: Powerful New Criticality Safety
Analysis Tools," pp. 447-453 in Proc. of The 7th International
Conference on Nuclear Criticality Safety (ICNC2003)," October
20-24, 2003, Tokai-mura, Japan. |
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S.
M. Bowman and J. E. Horwedel, "New SCALE Graphical Interface
for Criticality Safety," pp. 516-522 in Proc. of The 7th
International Conference on Nuclear Criticality Safety (ICNC2003)," October 20-24, 2003, Tokai-mura, Japan. |
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B. L. Broadhead and J. J. Wagschal,
"The Fission Spectrum Uncertainty," Proc. of ANS: PHYSOR 2004,
Chicago, IL, April 25-29, 2004. |
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B. L. Broadhead, B. T. Rearden, C. M. Hopper, J. J. Wagschal, and C.
V. Parks, “Sensitivity-and-Uncertainty-Based Criticality Safety
Validation Techniques,” Nucl. Sci. Eng. 146, 340-366 (2004). |
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B. L. Broadhead and J. C. Wagner, “Effective Biasing Schemes
for Duct Streaming Problems,” presented at the International
Conference on Radiation Shielding (ICRS-10), Funchal, Portugal, May 9-14, 2004. |
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B. L. Broadhead, Report of Foreign Travel to Funchal
and Kiev, May
7-23, 2004, FTR# 210000, June 2004. |
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M. D. DeHart and L. M. Petrie, “A Radioisotope Depletion Method Using Monte Carlo Transport with Variance Reduction and Error Propagation,” Proc. of ANS: PHYSOR 2004, Chicago, IL, April 25-29, 2004. |
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M. E. Dunn, D. F. Hollenbach, N. M. Greene, and L.
M. Petrie, “Point
KENO V.a: A Continuous-Energy Monte Carlo Code for Transport Applications,” Proc. of ANS: PHYSOR 2004, Chicago, Illinois, April 25-29, 2004. |
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M.
E. Dunn, N. M. Greene, and L. M. Petrie, "Continuous-energy
Version of KENO V.a for Criticality Safety Applications," pp. 439-446
in Proc. of The 7th International Conference on Nuclear Criticality
Safety (ICNC2003), October 20-24, 2003, Tokai-mura, Japan. |
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K.
R. Elam, Criticality Safety Study of UF6
and UO2F2 in 8-in.-Diameter Piping, ORNL/TM-2003/239,
UT-Battelle, LLC, Oak Ridge National Laboratory, October 2003. |
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S. Goluoglu, K. R. Elam, B. T. Rearden, B. L. Broadhead, and C. M. Hopper, Sensitivity Analysis Applied to the Validation of the 10B Capture Reaction in Nuclear Fuel Casks, NUREG/CR-6845 (ORNL/TM-2004/48), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., August 2004. |
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S.
Goluoglu, K. R. Elam, B. T. Rearden, B. L. Broadhead, C. M. Hopper, and
C.V. Parks, "Validation of the 10B Capture Reaction
in Nuclear Fuel Casks with Sensitivity Analysis," in Proc.
of American Nuclear Society: International ANS/ENS 2003 Winter Meeting
with cooperation from Nuclear Energy Institute on "Nuclear Technology:
Achieving Global Economic Growth While Safeguarding the Environment,"
November 16-20, 2003, New Orleans, Louisiana. Trans. Am. Nucl.
Soc. 89, 134-135 (2003). |
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S.
Goluoglu and C. M. Hopper,
Assessment of Degree of Applicability of Benchmarks for Gadolinium
Using KENO V.a and the 238-Group SCALE Cross-section Library, ORNL/TM-2003/106,
UT-Battelle, LLC, Oak Ridge National Laboratory, December 2003. |
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C. M. Hopper, Report of Foreign Travel to Obninsk, Russia,
March 15-19, 2004, XA 207659 (April 2004). |
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J. O. Johnson, Applicability of the Monte Carlo Neutral Particle Transport Code System (MCNP) to the Assessment of Nuclear Heating, ORNL/TM-2004/178, UT-Battelle, LLC, Oak Ridge National Laboratory, September 2004. |
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Y. Karni,
D. Regev, E. Greenspan, S. Goluoglu, L. M. Petrie,
and C. M. Hopper, “The SMORES Capability
for Minimum Critical Mass Determination,” in Proc. of The 7th International
Conference on Nuclear Criticality Safety (ICNC2003), October 20–24,
2003, Tokai-mura, Japan. |
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C. V. Parks and C. M. Hopper , “Technical Basis for Proposed Fissile Exemption Criteria for Transport Packages,” presented at the 14th International Symposium on the Packaging and Transportation of Radioactive Materials, Berlin, Germany, September 20-24, 2004. |
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C. V. Parks and J. C. Wagner, “Current Status and Potential Benefits
of Burnup Credit for Spent Fuel Transportation,” Proc. Of American
Nuclear Society, 14th Pacific Basin Conf., Honolulu,
HI, March 21-25, 2004. |
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B. T. Rearden, “Perturbation Theory Eigenvalue Sensitivity Analysis
With Monte Carlo Techniques,” Nucl. Sci. Eng. 146, 367-382 (2004). |
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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” to
be published in the Nuclear Technology Journal. |
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B.
T. Rearden, M. E. Dunn, and L. C. Leal, Joint Report of
Foreign Travel to Tokai-mura, Japan, October 17-24, 2003, FTR# 202858,
202504, and 202781 & 170462, November 2003. |
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B.
T. Rearden, C. M. Hopper, K. R. Elam, S. Goluoglu, and C. V. Parks,
"Applications of the TSUNAMI Sensitivity and Uncertainty Analysis Methodology,"
pp. 61-66 in Proc. of The 7th International Conference on Nuclear
Criticality Safety (ICNC2003)," October 20-24, 2003, Tokai-mura,
Japan. |
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D. A. Reed, D. E. Mueller, and R. G. Taylor, “Processing of Nuclear Ship Savannah Fuel,” presented at the 2004 ANS Annual Meeting in Pittsburgh, PA; Trans. Am. Nucl. Soc. 90, 124-125 (June 2004). |
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E. Sajo, and M. L. Williams, "Post-Implant Prostate Dosimetry Without Seed Localization," Med. Phys. 31(6), 1747 (2004). |
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J.
C. Wagner, "Impact of Soluble Boron Modeling for PWR Burnup
Credit Criticality Safety Analyses," in Proc. of American Nuclear
Society: International ANS/ENS 2003 Winter Meeting with cooperation from
Nuclear Energy Institute on "Nuclear Technology: Achieving Global
Economic Growth While Safeguarding the Environment," November
16-20, 2003, New Orleans, Louisiana. Trans. Am. Nucl. Soc. 89,
120-122 (2003). |
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J.
C. Wagner, Report of Foreign Travel to Tokyo and Tokai-mura,
Japan, October 12–24, 2003, FTR# 202191, November 2003. |
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J.
C. Wagner, "Evaluation of Burnup Credit for Accommodating PWR
Spent Nuclear Fuel in High-Capacity Cask Designs," pp. 684-689 in
Proc. of The 7th International Conference on Nuclear Criticality Safety
(ICNC2003), October 20-24, 2003, Tokai-mura, Japan. |
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J. F. Walker, Jr., P. A. Taylor, R. D. Spence, C. O. Slater, D. D. Walker, D. F. Bickford, S. Y. Lee, S. E. Aleman, L. L. Hamm, Small-Column Ion-Exchange Alternative to Remove 137Cs from Low-Curie Salt Waste: Summary Phase 1, ORNL/TM-2003/287, UT-Battelle, LLC, Oak Ridge National Laboratory, May 2004. |
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C.
F. Weber and C. M. Hopper, "Modeling Actinide Solution Densities
with the Pitzer Method," in Proc. of American Nuclear Society:
International ANS/ENS 2003 Winter Meeting with Cooperation from Nuclear
Energy Institute on "Nuclear Technology: Achieving Global Economic
Growth While Safeguarding the Environment," November 16-20,
2003, New Orleans, Louisiana; Trans. Am. Nucl. Soc. 89,
123-124 (2003). |
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R. M. Westfall and C. M. Hopper, Joint Report
of Foreign Travel to Paris, April 9-19, 2004, FTR#208273 and 208742, May 2004. |
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M. L. Williams, M. Asgari, and D. F. Hollenbach, CENTRUM: A One-Dimension Neuron Transport Code for Computing Pointwise Energy Spectra, NUREG/CR-0200, Rev. 7, Vol. 2, Sec. F18, prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., May 2004. |
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M. L. Williams, and D. F. Hollenbach, PMC: A Program to Produce Multigroup Cross Sections Using Pointwise Energy Spectra, NUREG/CR-0200, Rev. 7, Vol. 2, Sec. F19, prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., May 2004. |
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M. L. Williams, D. Ilas, E. Sajo, D. B. Jones, and K. E. Watkins, "Deterministic Photon Transport Calculations in General 3D Geometry for External Beam Radiation Therapy," Med. Phys. 30(12), 3183-3195 (2003). |
