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2000 Publications


E. Greenspan, Y. Karni, L. M. Petrie, and D. Regev, SWANS: A Prototypic SCALE Criticality Sequence for Automated Optimization Using the SWAN Methodology, ORNL/TM-1999/274 (UCBNE-4226), UT-Battelle, LLC, Oak Ridge National Laboratory, December 2000, Oak Ridge, Tenn.

B. L. Broadhead, "Value Rankings of Selected Critical Experiments for Burnup Credit Validations," Proc. of American Nuclear Society 2000 Winter Meeting, Washington, D.C., November 12-16, 2000, Trans. Am. Nucl. Soc. 83, 124-126 (2000).

B. L. Broadhead, R. L. Childs, and C. M. Hopper, "Illustrative Examples of Least-Squares Methods for Criticality Safety," Proc. of American Nuclear Society 2000 Winter Meeting, Washington, D.C., November 12-16, 2000, Trans. Am. Nucl. Soc. 83, 100-103 (2000).

B. L. Broadhead, "Uncertainty Analysis Methods for S/U Criticality Validation Techniques," Proc. of American Nuclear Society 2000 Winter Meeting, Washington, D.C., November 12-16, 2000, Trans. Am. Nucl. Soc. 83, 95-98 (2000).

B. L. Broadhead, C. M. Hopper, K. R. Elam, B. T. Rearden, and R. L. Childs, "Criticality Safety Applications of S/U Validation Methods," Proc. of American Nuclear Society 2000 Winter Meeting, Washington, D.C., November 12-16, 2000, Trans. Am. Nucl. Soc. 83, 107-113 (2000).

B. L. Broadhead and B. T. Rearden, "Foundations for Sensitivity-Based Criticality Validation Techniques," Proc. of American Nuclear Society 2000 Winter Meeting, Washington, D.C., November 12-16, 2000, Trans. Am. Nucl. Soc. 83, 93-95 (2000).

M. D. DeHart, "A Statistical Method for Estimating the Net Uncertainty in the Prediction of k Based on Isotopic Uncertainties," Proc. of American Nuclear Society 2000 Winter Meeting, Washington, D.C., November 12-16, 2000, Trans. Am. Nucl. Soc. 83, 121-122 (2000).

C. M. Hopper, "Guide for Nuclear Criticality Safety in the Storage of Fissile Materials," Proc. of American Nuclear Society 2000 Winter Meeting, Washington, D.C., November 12-16, 2000, Trans. Am. Nucl. Soc. 83, 151-152 (2000).

C. M. Hopper, "Overview of Sensitivity and Uncertainty Analysis Methods for Establishing Areas of Applicability and Subcritical Margins," Proc. of American Nuclear Society 2000 Winter Meeting, Washington, D.C., November 12-16, 2000, Trans. Am. Nucl. Soc. 83, 90-93 (2000).

N. L. Pruvost and R. M. Westfall, "ANSI/ANS-8.15-1981 (R95): Nuclear Criticality Control of Special Actinide Elements," Proc. of American Nuclear Society 2000 Winter Meeting, Washington, D.C., November 12-16, 2000, Trans. Am. Nucl. Soc. 83, 152-153 (2000).

B. T. Rearden and R. L. Childs, "Prototypical Sensitivity and Uncertainty Analysis Codes for Criticality Safety with the SCALE Code System," Proc. of American Nuclear Society 2000 Winter Meeting, Washington, D.C., November 12-16, 2000, Trans. Am. Nucl. Soc. 83, 98-100 (2000).

B. T. Rearden, C. M. Hopper, K. R. Elam, B. L. Broadhead, and P. B. Fox, "Prototypic Applications of Sensitivity and Uncertainty Analysis for Experiment Needs," Proc. of American Nuclear Society 2000 Winter Meeting, Washington, D.C., November 12-16, 2000, Trans. Am. Nucl. Soc. 83, 103-107 (2000).

J. C. Wagner and C. V. Parks, "Impact of Burnable Poison Rods on PWR Burnup Credit Criticality Safety Analyses," Proc. of American Nuclear Society 2000 Winter Meeting, Washington, D.C., November 12-16, 2000, Trans. Am. Nucl. Soc. 83, 130-134 (2000).

B. T. Rearden, "Sensitivity and Uncertainty Analysis for Nuclear Criticality Safety Using KENO in the SCALE Code System," Proc. Monte Carlo 2000 Conference - Advanced Monte Carlo Radiation Physics, Particle Transport Simulation Applications, Lisbon, Portugal, October 23-26, 2000.

M. B. Emmett and D. F. Hollenbach, "Current Status of the Oak Ridge Monte Carlo Codes: MORSE/SAS4 and KENO," Proc. Monte Carlo 2000 Conference - Advanced Monte Carlo Radiation Physics, Particle Transport Simulation Applications, Lisbon, Portugal, October 23-26, 2000.

M. B. Emmett, "MORSE: Present Capabilities and Future Directions," IRRMA'99 Meeting, 4th Topical Meeting on Industrial Radiation and Radioisotope Measurement Applications, Raleigh, N.C., October 3-7, 1999, in Applied Radiation and Isotopes, Vol. 53, No. 4-5, p. 863-866, October - November 2000. ISSN 0969-8043.

S. M. Bowman, W. C. Jordan, J. F. Mincey, C. V. Parks, and L. M. Petrie, Experience With the SCALE Criticality Safety Cross-Section Libraries, NUREG/CR-6686 (ORNL/TM-1999/322), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, October 2000.

B. L. Broadhead et al., Further Investigations of NIST Water Sphere Discrepancies, ORNL/TM-2000/173, UT-Battelle, LLC, Oak Ridge National Laboratory, Oak Ridge, Tenn., October 2000.

J. C. Wagner, M. D. DeHart, and B. L. Broadhead, Investigation of Burnup Credit Modeling Issues Associated With BWR Fuel, ORNL/TM-1999/193, UT-Battelle, LLC, Oak Ridge National Laboratory, Oak Ridge, Tenn., October 2000.

Y. Shimizu and C. M. Hopper, Computation Results from a Parametric Study to Determine Bounding Critical Systems of Homogeneously Water-Moderated Mixed-Plutonium - Uranium Oxides, ORNL/TM-2000/151, UT-Battelle, LLC, Oak Ridge National Laboratory, Oak Ridge, Tenn., October 2000.

B. Toghiani, J. S. Lindner, C. F. Weber, and R. D. Hunt, Modeling of Sulfate Double-salts in Nuclear Wastes, ORNL/TM-2000/317, UT-Battelle, LLC, Oak Ridge National Laboratory, Oak Ridge, Tenn., October 2000.

Sedat Goluoglu, Criticality Calculations of Fresh LEU and MOX Assemblies for Transport and Storage at the Balakovo Nuclear Power Plant, ORNL/TM-2000/286, UT-Battelle, LLC, Oak Ridge National Laboratory, Oak Ridge, Tenn., September 2000.

S. Goluoglu and J. Wesley Davis, "Shippingport PWR Fuel Criticality Analyses for Viability Evaluation of Codisposal in a Geologic Repository," Proc. of Spectrum 2000, International Conference on Nuclear and Hazardous Waste Management, Chattanooga, Tenn., September 24-28, 2000.

M. B. Emmett, "Calculational Benchmark Problems for VVER-1000 Mixed Oxide Fuel Cycle," Proc. of ANS2000 Radiation Protection and Shielding Division Topical Conference, Radiation Protection for our National Priorities: Medicine, the Environment and the Legacy, Spokane, Wash., September 17-20, 2000.

B. L. Broadhead and I. C. Gauld, "Rankings of Nuclide Importance in Spent Fuel for Shielding Applications," Proc. of Radiation Protection and Shielding Division Topical Conference, Radiation Protection for our National Priorities: Medicine, the Environment and the Legacy, Spokane, Wash., September 17-20, 2000.

A. Haghighat, G. E. Sjoden, and J. C. Wagner, "Advanced Three-Dimensional Deterministic and Monte Carlo Codes for Simulation of Real-Life Complex Nuclear Systems," 2000 Annual Meeting American Nuclear Society, San Diego, Calif., June 4-8, 2000, Trans. Am. Nucl. Soc. 82, 221-223 (2000).

R. Q. Wright, W. C. Jordan, and R. M. Westfall, "Critical Masses of Bare Metal Spheres Using SCALE/XSDRN," Proc. of American Nuclear Society 2000 Summer Meeting, San Diego, Calif., June 4-8, 2000, Trans. Am. Nucl. Soc. 82, 167-168 (2000).

R. Q. Wright, L. C. Leal, H. Derrien, N. M. Larson, and W. C. Jordan, "Data Testing of the ORNL Aluminum Evaluation," Proc. of American Nuclear Society 2000 Summer Meeting, San Diego, Calif., June 4-8, 2000, Trans. Am. Nucl. Soc. 82, 171-173 (2000).

S. M. Bowman, "The SCALE Web Site: Resources for the Worldwide Nuclear Criticality Safety Community," Proc. of American Nuclear Society 2000 Summer Meeting, San Diego, Calif., June 4-8, 2000, Trans. Am. Nucl. Soc. 82, 155-156 (2000).

J. C. Wagner and M. D. DeHart, "Investigation of BWR Depletion Calculations with SAS2H," Proc. of American Nuclear Society 2000 Summer Meeting, June 4-8, 2000, San Diego, Calif., Trans. Am. Nucl. Soc. 82, 173-176 (2000).

C. M. Hopper, "A Tool for Criticality Accident Emergency Planning, Training and Response," Proc. of International Workshop of the Safety of the Nuclear Fuel Cycle, May 2000, Tokyo, Japan.

S. M. Bowman and L. C. Leal, "ORIGEN-ARP: Automatic Rapid Process for Spent Fuel Depletion, Decay, and Source Term Analysis," NUREG/CR-0200, Rev. 6 (ORNL/NUREG/CSD-2R6), Vol. I, Part 2, Sect. D1, of SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation, May 2000. Available from Radiation Safety Information Computational Center at Oak Ridge National Laboratory as CCC-545.

S. M. Bowman et al., SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation, NUREG/CR-0200, Rev. 6 (ORNL/NUREG/CSD-2R6), Vols. I, II, III, May 2000. Available from Radiation Safety Information Computational Center at Oak Ridge National Laboratory as CCC-545.

O. W. Hermann and R. M. Westfall, ORIGEN-S: SCALE System Module to Calculate Fuel Depletion, Actinide Transmutation, Fission Product Buildup and Decay, and Associated Radiation Source Terms, Sect. F7 of SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation, Vols. I-III, NUREG/CR-0200, Rev. 6 (ORNL/NUREG/CSD-2/R6), May 2000. Available from Radiation Shielding Information Center at Oak Ridge National Laboratory as CCC-545.

N. M. Greene, L. M. Petrie, and R. M. Westfall, NITAWL-II: SCALE System Module for Performing Resonance Shielding and Working Library Production, Sect. F2 of SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation, Vols. I-III, NUREG/CR-0200, Rev. 6 (ORNL/NUREG/CSD-2/R6), May 2000. Available from Radiation Shielding Information Center at Oak Ridge National Laboratory as CCC-545.

C. M. Hopper, "The Value of and Need for International Criticality Safety Standards -- A Report on ISO TC 85/SC 5/WG 8 Activities," Proc. of International Workshop of the Safety of the Nuclear Fuel Cycle, May 2000, Tokyo, Japan.

M. E. Dunn and B. L. Broadhead, "PUFF-III: A Multigroup Covariance Processing Code for the AMPX Cross Section Processing System," Proc. of the PHYSOR 2000 ANS International Topical Meeting on Advances in Reactor Physics and Mathematics and Computation into the Next Millennium, Pittsburgh, Pa., May 7-12, 2000.

B. D. Murphy and R. T. Primm III, "Prediction of Spent MOX and LEU Fuel Composition and Comparison With Measurements," Proc. of the PHYSOR 2000 ANS International Topical Meeting on Advances in Reactor Physics and Mathematics and Computation into the Next Millennium, Pittsburgh, Pa., May 7-12, 2000.

B. T. Rearden, "SAMS: A Sensitivity Analysis Module for Criticality Safety Analysis Using Monte Carlo Techniques," Proc. of the PHYSOR 2000 ANS International Topical Meeting on Advances in Reactor Physics and Mathematics and Computation into the Next Millennium, Pittsburgh, Pa., May 7-12, 2000.

B. L. Broadhead, C. M. Hopper, and C. V. Parks, "Application of Covariance Data to Criticality Safety Data Validation," Proc. of Nuclear Data Covariance Workshop, April 22-23, 1999, Brookhaven National Laboratory, Upton, N.Y.

B. D. Murphy and L. A. Charlton, "Moderator Optimization for the Spallation Neutron Source," Proc. of ICONE8 8th International Conference on Nuclear Engineering, Baltimore, Md., April 2-6, 2000.

B. D. Murphy et al., Simulation of Low Enriched Uranium (LEU) Burnup in Russian VVER Reactors with the HELIOS Code Package, ORNL/TM-1999/168, Lockheed Martin Energy Systems Corp., Oak Ridge National Laboratory, Oak Ridge, Tenn., March 2000.

C. M. Hopper and B. L. Broadhead, "The Applicable Ranges of Bounding Curves & Data Task of the DOE Nuclear Criticality Safety Program, Status Review & Future Work Areas," DOE Nuclear Criticality Technology & Safety Workshop, Albuquerque, N. Mex., March 29, 2000.

D. E. Carlson, C. J. Withee, and C. V. Parks, "Spent Fuel Burnup Credit in Casks: An NRC Perspective," Proc. of the Twenty-Seventh Water Reactor Safety Information Meeting, Bethesda, Md., October 25-27, 1999, NUREG/CP-0169, pp. 419-436, March 2000.

S. M. Bowman, L. C. Leal, O. W. Hermann, and C. V. Parks, "ORIGEN-ARP, A Fast and Easy-to-Use Source Term Generation Tool," Ninth International Conference on Radiation Shielding ICRS-9, Tsukuba, Ibaraki, Japan, October 17-22, 1999, Journal Nucl. Sci. Technol. Supplement 1, 575-579 (March 2000).

B. L. Broadhead, M. B. Emmett, and J. S. Tang, "Implementation of Surface Detector Option in SCALE SAS4 Shielding Module," Ninth International Conference on Radiation Shielding ICRS-9, Tsukuba, Ibaraki, Japan, October 17-22, 1999, Journal Nucl. Sci. Technol. Supplement 1, 427-431 (March 2000).

M. B. Emmett, Calculational Benchmark Problems for VVER-1000 Mixed Oxide Fuel Cycle, ORNL/TM-1999/207, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, Oak Ridge, Tenn., March 2000.

O. W. Hermann, San Onofre PWR Data for Code Validation of MOX Fuel Depletion Analyses, ORNL/TM-1999/108/R1, LockHeed Martin Energy Research Corp., Oak Ridge National Laboratory, Oak Ridge, Tenn., March 2000.

I. C. Gauld, SCALE-4 Analysis of LaSalle Unit 1 BWR Commercial Reactor Critical Configurations, ORNL/TM-1999/247, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, Oak Ridge, Tenn., March 2000.

J. C. Wagner and M. D. DeHart, Review of Axial Burnup Distribution Considerations for Burnup Credit Calculations, ORNL/TM-1999/246, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, Oak Ridge, Tenn., March 2000.

R. M. Westfall, L. M. Petrie, R. C. Little, and E. K. Fujita, "The Analytical Methods Task of the DOE Nuclear Criticality Safety Program, Status Review & Future Work Areas," DOE Nuclear Criticality Technology & Safety Workshop, Albuquerque, N. Mex., March 29, 2000.

D. F. Hollenbach and P. B. Fox, Neutronics Benchmarks of Mixed-Oxide Fuels Using the SCALE/CENTRM Sequence, ORNL/TM-1999/299, U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, Oak Ridge, Tenn., February 2000.

C. V. Parks, M. D. DeHart, and J. C. Wagner, Review and Prioritization of Technical Issues Related to Burnup Credit for LWR Fuel, NUREG/CR-6665 (ORNL/TM-1999/303), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, February 2000.

O. W. Hermann, Benchmark of SCALE (SAS2H) Isotopic Predictions of Depletion Analyses for San Onofre PWR MOX Fuel, ORNL/TM-1999/326, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, Oak Ridge, Tenn., February 2000.

C. F. Weber, E. C. Beahm, D. D. Lee, and J. S. Watson, "A Solubility Model for Aqueous Solutions Containing Sodium, Fluoride, and Phosphate Ions," Ind. Eng. Chem. Res. 39(2), pp. 518-526, February 2000.

S. M. Bowman, SCALE Newsletter No. 21, January 2000.

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