Reactor and Nuclear Systems Division
Author(s) / Report Title / Publication Number / Date
J. L. McDuffee, T. D. Burchell, D. W. Heatherly, and K. R. Thoms, "Experimental Plan and Design of Two Experiments for Graphite Irradiation at Temperatures up to 1500oC in the Target Region of the High Flux Isotope Reactor," J. Nucl. Matls. 381, 114-118 (2008).
J. L. McDuffee, T. D. Burchell, D. W. Heatherly, and K. R. Thoms, "Preliminary Design of a Graphite Irradiation Tensile Creep Experiment in the Target Region of the High Flux Isotope Reactor," J. Nucl. Matls. 381, 119-123 (2008).
R. C. Little et al., "Low-fidelity Covariance Project," Nuclear Data Sheets 109, 2828 (2008).
S. J. Ball, M. Richards, and S. Shepelev, "Sensitivity Studies of Air Ingress Accidents in Modular HTGRs," Nuclear Engineering and Design 238, 2935-2942 (2008).
I. Remec, D. C. Glasgow, J. R. Haines, and J. O. Johnson, "Proton induced activation in mercury: Comparison of measurements and calculations," Reactor Dosimetry: 12th International Symposium Book Series: American Society for Testing and Materials Special Technical Publication 1490, 220-227 (2008).
T. Uckan et al., "Use of Californium-252 Neutron Sources for a Continuous Monitoring of Uranium-235 Mass Flow," Health Physics Society Midyear Meeting, Oakland, Calif., January 27-30, 2008.
A. Alpan and A. Haghighat, "Use of CPXSD for generation of effective fast multigroup libraries for pressure vessel fluence calculations," Reactor Dosimetry: 12th International Symposium Book Series: American Society for Testing and Materials Special Technical Publication, 1490, 313-320 (2008).
J. J. Carbajo, A. L. Qualls, and J. L. McDuffee, "Comparison of RELAP5-3D/ATHENA and ANSYS/FLOTRAN Thermal-hydraulic Results," Trans. Am. Nucl. Soc. 98, 457-459 (2008).
J. J. Carbajo, "Applicability of Heat Transfer Coefficient Correlations to Single-Phase Convection in Liquid Metals," Trans. Am. Nucl. Soc. 98, 460-462 (2008).
E. L. Popov and G. L. Yoder, Jr., "IRIS pressurizer fluid dynamics and heat transfer analyses," Nuclear Engineering and Design 238(1), 81-89 (2008).
M. A. Smith, A. W. Fentiman, and I. L. Larsen, "Fate of Co-60 at a sludge land application," Journal of Environmental Radioactivity 99(10), 1611 (2008).
A. D. Carlson, et al., "Covariances Obtained from an Evaluation of the Neutron Cross Section Standards," Nucl. Data Sheets 109(12), 2834-2839, December 2008.
L. C. Leal, G. Arbanas, H. Derrien, and D. Wiarda, "Resonance Region Covariance Analysis Method and New Covariance Data for Th-232, U-233, U-235, U-238, and Pu-239," Nucl. Data Sheets 109(12), 2868-2873, December 2008.
A. Trkov, R. Capote, I. Kodeli, and L. C. Leal, "Evaluation of Tungsten Nuclear Reaction Data with Covariances," Nucl. Data Sheets 109(12), 2905-2909, December 2008.
B. Riemer et al., "Mercury Target Development at SNS," American Nuclear Society Winter Meeting and Nuclear Technology Expo, Reno, Nev., November 9-13, 2008.
B. L. Kirk, “The Radiation Safety Information Computational Center (RSICC): A Resource for Nuclear Science Applications,” Proc. IEEE 2008 Nuclear Science Symposium, Dresden, Germany, October 19-25, 2008.
S. M. Bowman, KENO-VI Primer: A Primer for Criticality Calculations with SCALE/KENO-VI Using GeeWiz, ORNL/TM-2008/069, Oak Ridge National Laboratory, Oak Ridge, Tenn., September 2008.
D. L. Williams, Jr., Grid-Appropriate Reactors - Licensing Issues form the Multinational Design Evaluation Program (MDEP) and Recent NRC Reviews of Small Reactor Designs, ORNL/TM-2008/172, Oak Ridge National Laboratory, Oak Ridge, Tenn., September 2008.
R. J. Ellis, J. C. Gehin, J. L. McDuffee, and R. W. Hobbs, "Analysis of a Fast Spectrum Irradiation Facility in the High Flux Isotope Reactor," Proc. PHYSOR 2008: International Topical Meeting on Advances in Reactor Physics, Interlaken, Switzerland, September 14-19, 2008.
K. Korsah and R. T. Wood, "Key Regulatory Issues for Digital Instrumentation and Control Systems at Nuclear Power Plants," ISSNP/CSEPC/ISOFIC2008, Heilongjiang, China, September 8-10, 2008.
R. G. McClarren, T. M. Evans, R. B. Lowrie, and J. D. Densmore, "Semi-implicit time integration for PN thermal radiative transfer," Journal of Computational Physics 227(16), 7561-7586, August 2008.
S. M. Bowman, SCALE Newsletter, Vol. 38, July 2008.
M. L. Williams, S. M. Bowman, M. E. Dunn, and S. Goluoglu, "Verification and Validation Techniques in SCALE 6," Workshop on Verification and Validation Techniques, Idaho Falls, Idaho, July 24, 2008.
J. A. Mullens, B. R. Grogan, D. E. Archer, and J. T. Mihalczo, "Shipping Anomaly from NMIS Imaging," 49th Annual Meeting of the Institute of Nuclear Materials Management (INMM), Nashville, Tenn., July 13-19, 2008.
J. L. Ladd-Lively, "Status Update: Uranyl Nitrate Calibration Loop Equipment (UNCLE) at ORNL," 49th Annual Meeting of the Institute of Nuclear Materials Management (INMM), Nashville, Tenn., July 13-19, 2008.
D. K. Felde, M. W. Wendel, and B. Riemer, "Development of a gas layer to mitigate cavitation damage in liquid mercury spallation targets," Journal of Nuclear Materials 377(1), 155-161, June 2008.
D. Wiarda, G. Arbanas, L. C. Leal, and M. E. Dunn, "Recent Advances with the AMPX Covariance Processing Capabilities in PUFF-IV," Workshop on Neutron Cross Section Covariance, Port Jefferson, N.Y., June 24-27, 2008.
M. L. Williams and B. T. Rearden, "SCALE-6 Sensitivity/Uncertainty Methods and Covariance Data," Workshop on Neutron Cross Section Covariances, Port Jefferson, N.Y., June 24-27, 2008.
C. W. Forsberg, “High-Temperature Reactors for Underground Liquid-Fuels Production with Direct Carbon Sequestration,” Proceedings of ICAPP ’08, Anaheim, Calif., June 8–12, 2008.
C. W. Forsberg, P. F. Peterson, and R. A. Kochendarfer, “Design Options for the Advanced High-Temperature Reactor,” Proceedings of ICAPP ’08, Anaheim, Calif., June 8–12, 2008.
B. L. Kirk, “Update on the Activities of the Computational Medical Physics Working Group (CMPWG),” Proc. Shielding Aspects of Accelerators and Target Irradiation Facilities, SATIF-9, Oak Ridge, Tenn., April 21-23, 2008.
G. Ilas and I. C. Gauld, Analysis of Experimental Data for High Burnup PWR Spent Fuel Isotopic Validation-MALIBU Program (UOx Fuel), ORNL/TM-2008/013, Oak Ridge National Laboratory, Oak Ridge, Tenn., March 2008.
R. Q. Wright and C. M. Hopper, "Calculation of the minimum critical mass of fissile nuclides," Nuclear Science and Engineering 158(2), 203-209 (2008).
G. Ilas and I. C. Gauld, "SCALE Analysis of CLAB Decay Heat Measurements for LWR Spent Fuel Assemblies," Annals of Nuclear Energy, 35(1), 37-48, January 2008.
S. M. Bowman, SCALE Newsletter,Vol. 37, January 2008.