Reactor and Nuclear Systems Division

Reactor and Nuclear Systems Division
2002 Publications

Author(s) / Report Title / Publication Number / Date

C. M. Hopper, L. M. Petrie, L. J. Ott, and C. V. Parks, Design Parameters for a Natural Uranium UO3- or U3O8-Fueled Nuclear Reactor, ORNL/TM-2002/240, UT-Battelle, LLC, Oak Ridge National Laboratory, Oak Ridge, Tenn., November 2002.

B. D. Murphy and R. T. Primm, III, "Simulation of Mixed-Oxide and Low-Enriched Uranium Fuel Burnup in a Pressurized Water Reactor and Validation Against Destructive Analysis Results," Nucl. Sci. Eng. 142, 258-269 (November 2002).

D. F. Hollenbach, L. M. Petrie, B. T. Rearden, and S. M. Bowman, "KENO Postprocessor Analysis and Plotting Capabilities," Proc. of American Nuclear Society 2002 Winter Meeting "Building the World Nuclear Community -- Strategies for the Deployment of New Nuclear Technologies," Wash., D.C., November 17-21, 2002, Trans. Am. Nucl. Soc. 87, 270-272 (2002).

I. C. Gauld, E. F. Shores, and R. T. Perry, "New Neutron Source Algorithms in the ORIGEN-S Code," Proc. of American Nuclear Society 2002 Winter Meeting "Building the World Nuclear Community -- Strategies for the Deployment of New Nuclear Technologies," Wash., D.C., November 17-21, 2002, Trans. Am. Nucl. Soc. 87, 406-407 (2002) --Highlights of RPSD 2002.

M. D. DeHart, "New Two-Dimensional Deterministic Criticality Safety Capabilities in SCALE 5," Proc. of American Nuclear Society 2002 Winter Meeting "Building the World Nuclear Community -- Strategies for the Deployment of New Nuclear Technologies," Wash., D.C., November 17-21, 2002, Trans. Am. Nucl. Soc. 87, 272-273 (2002).

S. M. Bowman et al., "An Overview of What's New in SCALE 5," Proc. of American Nuclear Society 2002 Winter Meeting "Building the World Nuclear Community -- Strategies for the Deployment of New Nuclear Technologies," Wash., D.C., November 17-21, 2002, Trans. Am. Nucl. Soc. 87, 265-268 (2002).

M. E. Dunn and L. C. Leal, "Calculating Probability Tables for the Unresolved-Resonance Region Using Monte Carlo Methods," Proc. of International Conference on the New Frontiers of Nuclear Technology: Reactor Physics, Safety and High Performance Computing (PHYSOR 2002), Seoul, Korea, October 7-10, 2002. Will also be published in Nucl. Sci. Eng.

M. E. Dunn, "Computational Experience with the Reich-Moore Resolved-Resonance Equations in the AMPX Cross-Section Processing System," Nucl. Sci. Eng. 142(1), 48-56 (September 2002).

C. V. Parks, B. D. Murphy, L. M. Petrie, and C. M. Hopper, Plutonium Production Using Natural Uranium From the Front-End of the Nuclear Fuel Cycle, ORNL/TM-2002/118, UT-Battelle, LLC, Oak Ridge National Laboratory, Oak Ridge, Tenn., September 2002.

J. C. Wagner and C. E. Sanders, "Investigation of the Effect of Fixed Absorbers on the Reactivity of PWR Spent Nuclear Fuel for Burnup Credit," Nucl. Technol. 139(2), 91-126 (August 2002).

S. Goluoglu and R. T. Primm, III, "Criticality Analysis of MOX and LEU Assemblies for Transport and Storage at the Balakovo Nuclear Power Plant," Nucl. Technol. 139, 80-88 (July 2002).

S. M. Bowman, SCALE Newsletter, No. 26, July 2002.

S. Goluoglu et al., "SMORES -- A New SCALE Sequence for the Determination of Bounding Curves and Data," Proc. of American Nuclear Society, 2002 Annual Meeting "The Revival of the Nuclear Energy Option," Hollywood, Fla., June 9-13, 2002, Trans. Am. Nucl. Soc. 86, 114-116 (June 2002).

B. D. Murphy, Energy-Deposition and Damage Calculations in Core-Vessel Inserts at the Spallation Neutron Source, SNS 107030600-DA0001-R00 (ORNL/TM-2002/125), UT-Battelle, LLC, Oak Ridge National Laboratory, Oak Ridge, Tenn., June 2002.

B. T. Rearden and K. R. Elam, Investigations and Recommendations on the Use of Existing Experiments in Criticality Safety Analysis of Nuclear Fuel Cycle Facilities for Weapons-Grade Plutonium, ORNL/TM-2001/262, UT-Battelle, LLC, Oak Ridge National Laboratory, Oak Ridge, Tenn., June 2002.

M. E. Dunn and N. M. Greene, "AMPX-2000: A Cross-Section Processing System for Generating Nuclear Data for Criticality Safety Applications," Proc. of American Nuclear Society, 2002 Annual Meeting "The Revival of the Nuclear Energy Option," Hollywood, Fla., June 9-13, 2002, Trans. Am. Nucl. Soc. 86, 118-119 ( 2002).

C. E. Sanders and M. D. DeHart, "Computational Benchmark of SAS2D Against Spent Fuel Samples From the Takahama-3 Reactor," Proc. of American Nuclear Society, 2002 Annual Meeting "The Revival of the Nuclear Energy Option," Hollywood, Fla., June 9-13, 2002, Trans. Am. Nucl. Soc. 86, 100-102 (2002).

C. E. Sanders and John C. Wagner, "Investigation of Average and Pin-Wise Burnup Modeling of PWR Fuel," Proc. of American Nuclear Society, 2002 Annual Meeting "The Revival of the Nuclear Energy Option," Hollywood, Fla., June 9-13, 2002, Trans. Am. Nucl. Soc. 86, 98-100 (2002).

R. M. Westfall and K. R. Yates, "Derivation of Updated 238Pu Subcritical Limits for ANS-8.15," Proc. of American Nuclear Society, 2002 Annual Meeting "The Revival of the Nuclear Energy Option," Hollywood, Fla., June 9-13, 2002, Trans. Am. Nucl. Soc. 86, 56-57 (2002).

J. M. Herndon and D. F. Hollenbach, "Foundations of Nuclear Geophysics," Proc. of 2002 Spring American Geophysical Union Meeting, Washington, D.C., May 28-31, 2002.

P. B. Fox and L. M. Petrie, Validation and Comparison of KENO V.a and KENO-VI, ORNL/TM-2001/110, UT-Battelle, LLC, Oak Ridge National Laboratory, Oak Ridge, Tenn., May 2002.

S. M. Bowman and J. E. Horwedel, "ESPN: SAS4 Shielding Input Processor for SCALE," Proc. of American Nuclear Society 12th Biennial RPSD Topical Meeting, Santa Fe, N. Mex., April 14-18, 2002.

S. M. Bowman, J. E. Horwedel, I. C. Gauld, and D. L. Barnett, "ORIGEN-ARP: A New Windows PC Package for ORIGEN Users," Proc. of American Nuclear Society 12th Biennial RPSD Topical Meeting, Santa Fe, N. Mex., April 14-18, 2002.

I. C. Gauld, E. F. Shores, and R. T. Perry, "New Neutron Source Algorithms in the ORIGEN-S Code," Proc. of American Nuclear Society 12th Biennial RPSD Topical Meeting, Santa Fe, N. Mex., April 14-18, 2002.

B. L. Broadhead, "Estimation of the Dose Effects of Gamma-Ray Streaming Through Cracks in the MVST Storage/Disposal Cask," Proc. of American Nuclear Society 12th Biennial RPSD Topical Meeting, Santa Fe, N. Mex., April 14-18, 2002.

J. C. Wagner, "An Automated Deterministic Variance Reduction Generator for Monte Carlo Shielding Applications," Proc. of American Nuclear Society 12th Biennial RPSD Topical Meeting, Santa Fe, N. Mex., April 14-18, 2002.

S. Goluoglu and C. M. Hopper, DOE NCSP Review of TRUPACT-II/HalfPACT Fissile Limits, ORNL/TM-2002/58, UT-Battelle, LLC, Oak Ridge National Laboratory, Oak Ridge, Tenn., March 2002.

Japan Atomic Energy Research Institute (JAERI), Technical Development on Burn-up Credit for Spent LWR Fuel, (Eds.) Y. Nakahara, K. Suyama, and T. Suzaki, JAERI-Tech 2000-071, Tokai-mura, Naka-gun, Ibaraki-ken, Japan, October 2000. [ORNL/TR-2001/01 English Translation, Oak Ridge National Laboratory, January 2002] -- I. C. Gauld (ORNL) coordinated translation by JLS Language Corporation, Menlo Park, Calif.

S. M. Bowman, SCALE Newsletter, No. 25, January 2002.