Oak Ridge National Laboratory

Nuclear Modeling, Design, and Safety
2006


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

Charles W. Forsberg, Per F. Peterson and Haihua Zhao, “Sustainability and Economics of the Advanced High-Temperature Reactor,” J. Energy  Eng. Vol. 132, No. 3, pp. 109-115 (December 2006).

Charles W. Forsberg and Leslie R. Dole, “Cermet Spent Nuclear Fuel Casks and Waste Packages,” in Proc. of the Materials Research Society Scientific Basis for Nuclear Waste Management, November 27–December 1, 2006, Boston, Massachusetts.

Charles W. Forsberg and Michael J. Driscol, “Specialized Disposal Sites for Different Reprocessing Plant Wastes,” in Proc. of the Materials Research Society Scientific Basis for Nuclear Waste Management, November 27–December 1, 2006, Boston, Massachusetts.

E. J. Lahoda, C. W. Forsberg, and D. F. McLaughlin, “A Low-Greenhouse-Impact Hydrogen-Based Liquid-Fuels Future,” CD-ROM, Proc.of American Institute of Chemical Engineers Annual Meeting, November 12-17, 2006, San Francisco, California.

Charles W. Forsberg, Venugopal K. Varma, and Thomas W. Burgess, “Three-Dimensional Imaging and Precision Metrology for Liquid-Salt-Cooled Reactors,” CD-ROM, Proc. of 5th International Topical Meeting on Nuclear Plant Instrumentation and Controls, and Human Machine Interface Technology, Embedded Topical in American Nuclear Society 2006 Winter Meeting, November 12–16, 2006, Albuquerque, New Mexico.

Charles. W. Forsberg, “Economic Implications of Peak vs. Base-Load Electric Costs on Nuclear Hydrogen Systems,” CD-ROM, 2006 American Institute of Chemical Engineers Annual Meeting, November 12–17, 2006, San Francisco, California.

D. F. Hollenbach, L. M. Petrie, and S. M. Bowman, “Advances in the KENO-VI Geometry Package,” ANS 2006 Winter Meeting “Ensuring the Future in Times of Change: Nonproliferation and Security,” November 12–16, 2006, Albuquerque, New Mexico. Trans. Am. Nucl. Soc., 95, 296–298 (2006).

James E. Horwedel, Stephen M. Bowman, and Daniel F. Hollenbach, “New Capabilities to Calculate Volumes of SCALE/KENO-VI Geometry Models,” ANS 2006 Winter Meeting “Ensuring the Future in Times of Change: Nonproliferation and Security,” November 12–16, 2006, Albuquerque, New Mexico. Trans. Am. Nucl. Soc., 95, 287–289 (2006).

Douglas E. Peplow, Stephen M. Bowman, James E. Horwedel, and John C. Wagner, “Monaco/MAVRIC: Computational Resources for Radiation Protection ad Shielding in SCALE,” ANS 2006 Winter Meeting “Ensuring the Future in Times of Change: Nonproliferation and Security,” November 12–16, 2006, Albuquerque, New Mexico. Trans. Am. Nucl. Soc., 95, 669–671 (2006).

SCALE:  A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluations, ORNL/TM-2005/39, Version 5.1, Vols. I–III, November 2006.  Available from Radiation Safety Information Computational Center at Oak Ridge National Laboratory as CCC-732.

S. M. Bowman and D. F. Gill, “Validation of Standardized Computer Analyses for Licensing Evaluation/TRITON Two-Dimensional and Three-Dimensional Models for Light Water Reactor Fuel,” B153.pdf in Proc. of PHYSOR–2006, American Nuclear Society Topical Meeting on Reactor Physics: Advances in Nuclear Analysis and Simulation, September 10–14, 2006, Vancouver, British Columbia, Canada.

C. W. Forsberg, Assessment of Nuclear-Hydrogen Synergies with Renewable Energy Systems and Coal Liquefaction Processes, ORNL/TM-2006/114, UT-Battelle, LLC, Oak Ridge National Laboratory, August 2006.

Ian C. Gauld, Stephen M. Bowman, Brian D. Murphy, and P. Schwalbach, “Applications of ORIGEN to Spent Fuel Safeguards and Non-Proliferation,” 431_gauldian.pdf in Proc. of INMM 47th Annual Meeting, July 16–20, 2006, Nashville, Tennessee.

S. M. Bowman, SCALE Newsletter, No. 34, July 2006.

C. W. Forsberg, D. T. Ingersoll, P. F. Peterson, H. Zhao, J. E. Cahalan, T. Taiwo, J. A. Enneking, R. A. Kochendarfer, and P. E. MacDonald, Refueling Options and Considerations for Liquid-Salt-Cooled Very High-Temperature Reactors, ORNL/TM-2006/92, UT-Battelle, LLC, Oak Ridge National Laboratory, June 2006.

C. W. Forsberg, "High-Temperature Nuclear Reactors for In-Situ Recovery of Oil from Oil Shale," pp. 2322–28 in Proceedings of the 2006 International Congress on Advances in Nuclear Power Plants (ICAPP '06) , June 4–8, 2006, Reno, Nevada.

C. W. Forsberg, "Developments in Molten Salt and Liquid-Salt-Cooled Reactors," pp. 806–16 in Proceedings of the 2006 International Congress on Advances in Nuclear Power Plants (ICAPP '06) , June 4–8, 2006, Reno, Nevada.

C. W. Forsberg, "Molten-Salt-Reactor Technology Gaps," pp. 699–705 in Proceedings of the 2006 International Congress on Advances in Nuclear Power Plants (ICAPP '06) , June 4–8, 2006, Reno, Nevada.

C. W. Forsberg, "Alternative Passive Decay-Heat System for the Advanced High-Temperature Reactor," pp. 638–49 in Proceedings of the 2006 International Congress on Advances in Nuclear Power Plants (ICAPP '06) , June 4–8, 2006, Reno, Nevada.

D. T. Ingersoll and C. W. Forsberg, "Overview and Status of the Advanced High-Temperature Reactor," pp. 598–606 in Proceedings of the 2006 International Congress on Advances in Nuclear Power Plants (ICAPP '06) , June 4–8, 2006, Reno, Nevada.

C. W. Forsberg, “Fuel Characteristics and Requirements for the Advanced High-Temperature Reactor,” 2006 ANS Annual Meeting, Embedded Topical: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors, June 4–8, 2006, Reno, Nevada. Trans. Am. Nucl. Soc., 94, 645–647 (2006).

C. V. Parks, J. C. Wagner, and D. E. Mueller, “Full Burnup Credit in Transport and Storage Casks: Benefits and Implementation,” pp. 1299–1308 in Proc. of the 11th International High-Level Radioactive Waste Management Conference (IHLRWM), April 30–May 4, 2006, Las Vegas, Nevada.

V. I. Shapovalov, V. Z. Matveev, A. G. Semenov, V. M. Sergeyev, V. K. Orlov, V. T. Gotovchikov, V. A. Seredenko, V. V. Shatalov, Jonathan M. Haire and Charles W. Forsberg, “Conception of Universal Cask Based on Cermet for SNF Transportation and Storage,” pp. 885–889 in Proc. of the 11th International High-Level Radioactive Waste Management Conference (IHLRWM) April 30–May 4, 2006, Las Vegas, Nevada.

V. T. Gotovchikov, V. A. Seredenko, V. V. Shatalov, V. N. Kaplenkov, A. S. Shulgin, V. K. Saranchin, M. A. Borik and C. W. Forsberg, “Melted and Granulated Depleted Uranium Dioxide for Use in Containers for Spent Nuclear Fuel,” pp. 866–870 in Proc. of the 11th International High-Level Radioactive Waste Management Conference (IHLRWM) April 30–May 4, 2006, Las Vegas, Nevada.

C. W. Forsberg,Advanced-High-Temperature-Reactor Spent-Fuel Characteristics and Repository Impacts,” pp. 798–804 in Proc. of the 11th International High-Level Radioactive Waste Management Conference (IHLRWM) April 30–May 4, 2006, Las Vegas, Nevada.

C. W. Forsberg and T. N. Tiegs, “Manufacturing and Economic Studies for DUO 2-Steel Cermet Spent Fuel Casks,” pp. 1292–1298 in Proc. of the 11th International High-Level Radioactive Waste Management Conference (IHLRWM) April 30–May 4, 2006, Las Vegas, Nevada.

C. V. Parks, J. C. Wagner, and D. E. Mueller, “Full Burnup Credit in Transport and Storage Casks: Benefits and Implementation,” pp. 1299–1308 in Proc. of the 11th International High-Level Radioactive Waste Management Conference (IHLRWM), April 30–May 4, 2006, Las Vegas, Nevada.

C. W. Forsberg, “Synergistic Benefits of a Nuclear-Renewables Hydrogen Economy,” Paper 2622 in Proc. of 17th Annual U.S. Hydrogen Conference, March 12–16, 2006, Long Beach, California.

C. W. Forsberg, A Chapter XXVII: The Advanced High-Temperature Reactor - AHTR @ ed. V. V. Kuznetsov,  Status of Innovative Small and Medium Sized Reactor Designs 2005: Reactors with Conventional Refueling Systems, IAEA-TECDOC-1485, International Atomic Energy Agency, Vienna (March 2006).

S. M. Bowman, SCALE Newsletter, No. 33, January 2006.


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