Reactor and Nuclear Systems Division

Reactor and Nuclear Systems Division
2006 Publications

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

C. W. Forsberg, P. F. Peterson, and H. Zhao, “Sustainability and Economics of the Advanced High-Temperature Reactor,” J. Energy  Eng. 132(3), 109-115 (December 2006).

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

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

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, San Francisco, Calif., November 12-17, 2006.

C. W. Forsberg, V. K. Varma, and T. 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, Albuquerque, N. Mex., November 12–16, 2006.

C. 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, San Francisco, Calif., November 12–17, 2006.

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,” Albuquerque, N. Mex., November 12–16, 2006, Trans. Am. Nucl. Soc. 95, 296–298 (2006).

J. E. Horwedel, S. M. Bowman, and D. 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,” Albuquerque, N. Mex., November 12–16, 2006, Trans. Am. Nucl. Soc. 95, 287–289 (2006).

D. E. Peplow, S. M. Bowman, J. E. Horwedel, and J. 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,” Albuquerque, N. Mex., November 12–16, 2006, 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,” Proc. of PHYSOR–2006, American Nuclear Society Topical Meeting on Reactor Physics: Advances in Nuclear Analysis and Simulation, Vancouver, B. C., September 10–14, 2006.

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, Oak Ridge, Tenn., August 2006.

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

I. C. Gauld, S. M. Bowman, B. D. Murphy, and P. Schwalbach, “Applications of ORIGEN to Spent Fuel Safeguards and Non-Proliferation,” Proc. of INMM 47th Annual Meeting, July 16–20, 2006, Nashville, Tenn.

B. L. Broadhead, M. L. Williams, and J. J. Wagschal, "Generalized Linear Least-Squares Adjustment, Revisited," J. ASTM International 3(7), 340-347 (June 2006).

C. W. Forsberg et al., Refueling Options and Considerations for Liquid-Salt-Cooled Very High-Temperature Reactors, ORNL/TM-2006/92, Oak Ridge National Laboratory, Oak Ridge, Tenn., June 2006.

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

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

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

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

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

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, Reno, Nev., June 4–8, 2006, 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,” Proc. of the 11th International High-Level Radioactive Waste Management Conference (IHLRWM), Las Vegas, Nev., April 30–May 4, 2006.

V. I. Shapovalov et al., “Conception of Universal Cask Based on Cermet for SNF Transportation and Storage,” Proc. of the 11th International High-Level Radioactive Waste Management Conference (IHLRWM), Las Vegas, Nev., April 30–May 4, 2006.

V. T. Gotovchikov et al., “Melted and Granulated Depleted Uranium Dioxide for Use in Containers for Spent Nuclear Fuel,” Proc. of the 11th International High-Level Radioactive Waste Management Conference (IHLRWM), Las Vegas, Nev., April 30–May 4, 2006.

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

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

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

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).

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

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