Oak Ridge National Laboratory

Nuclear Modeling, Design, and Safety
2007 Publications


Author(s) / Report Title / Publication Number / Date
S. Goluoglu, S. M. Bowman, and M. E. Dunn, “KENO Monte Carlo Code Capabilities,” The American Nuclear Society and the European Nuclear Society 2007 International Conference on Making the Renaissance Real, November 11–15, 2007, Washington, D.C. Trans. Am. Nucl. Soc. 97, 592–594 (2007).
S. M. Bowman, “Overview of the SCALE Code System,” The American Nuclear Society and the European Nuclear Society 2007 International Conference on Making the Renaissance Real, November 11–15, 2007, Washington, D.C. Trans. Am. Nucl. Soc . 97, 589–591 (2007).
M. L. Williams, S. M. Bowman, and C. V. Parks, “Plans for Future SCALE Development Beyond Version 6.0,” The American Nuclear Society and the European Nuclear Society 2007 International Conference on Making the Renaissance Real, November 11–15, 2007, Washington, D.C. Trans. Am. Nucl. Soc. 97, 606–607 (2007).
Charles W. Forsberg, “Changing Biomass, Fossil, and Nuclear Fuel Cycles for Sustainability,” P101958.pdf in Proc. of 2007 AIChE Annual Meeting, November 4–9, 2007, Salt Lake City, Utah.
Charles W. Forsberg, “Meeting U.S. Liquid Transport Fuel Needs with a Nuclear Hydrogen Biomass System,” P85370.pdf in Proc. of 2007 AIChE Annual Meeting, November 4–9, 2007, Salt Lake City, Utah.
Charles W. Forsberg and Maximilian B. Gorensek, “Relative Economic Incentives for Hydrogen from Nuclear, Renewable, and Fossil Energy Sources,” P101552.pdf in Proc. of 2007 AIChE Annual Meeting, November 4–9, 2007, Salt Lake City, Utah.

Charles W. Forsberg, “Thermal- and Fast-Spectrum Molten Salt Reactors for Actinide Burning and Fuels Production,” pp. 1214–1225 in Proc. of Global 2007: Advanced Nuclear Fuel Cycles and Systems, September 9–13, 2007, Boise, Idaho, American Nuclear Society, La Grange Park, Illinois.

Charles W. Forsberg, “A Modular Radiant-Heat-Initiated Passive Decay-Heat-Removal System for Salt-Cooled Reactors,” pp. 866–871 in Proc. of Global 2007: Advanced Nuclear Fuel Cycles and Systems, September 9–13, 2007, Boise, Idaho, American Nuclear Society, La Grange Park, Illinois.

James C. Conklin and Charles W. Forsberg, “Base-Load and Peak Electricity from a Combined Nuclear Heat and Fossil Combined-Cycle Power Plant,” pp. 1585–1590 in Proc. of Global 2007: Advanced Nuclear Fuel Cycles and Systems, September 9–13, 2007, Boise, Idaho, American Nuclear Society, La Grange Park, Illinois.

M. Jonathan Haire and Charles W. Forsberg, “Tags to Track Illicit Uranium and Plutonium,” pp. 1649–1656 in Proc. of Global 2007: Advanced Nuclear Fuel Cycles and Systems, September 9–13, 2007, Boise, Idaho, American Nuclear Society, La Grange Park, Illinois.

C. W. Forsberg and James C. Conklin, Hydrogen-or-Fossil-Combustion Nuclear Combined-Cycle Systems for Base- and Peak-Load Electricity Production, ORNL-6980, UT-Battelle, LLC, Oak Ridge National Laboratory, September 2007.

C. W. Forsberg, M. Gorensek, P. Pickard, and S. Herring, Next-Generation Nuclear Plant Phenomena Identification and Ranking Tables (PIRTs)—Volume 6:  Process Heat and Hydrogen Co-Generation PIRTS, NUREG/CR-6944, Vol. 6  (ORNL/TM-2007/147/V6) U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, September 2007.

H. Akkurt, J. C. Wagner, and K. F. Eckerman, “Hand-Held Instruments for Landmine Detection: View from Radiation Dosimetry,” Nuclear Instruments and Methods in Physics Research A, 579, 391–394, 2007.

S. M. Bowman, SCALE Newsletter, No. 36, July 2007.
H. Akkurt, K. F. Eckerman, D. Wiarda, J. C. Wagner, and S. Sherbini, “Development of a Computational Phantom with Moving Arms and Legs for Radiation Dose Assessment,” presented at the The 52nd Annual Meeting of the Health Physics Society, July 8–12, 2007, Portland, Oregon.
Juan J. Carbajo, Grady L. Yoder, and Charles W. Forsberg, “RELAP5-3D Model of the Advanced High-Temperature Reactor (AHTR),” American Nuclear Society 2007 Annual Meeting “It’s All About the People: The Future of Nuclear,” June 24–28, 2007, Boston, Massachusetts. Trans. Am. Nucl. Soc , 96, p.797–799 (2007).
Juan J. Carbajo, Grady L. Yoder, and Charles W. Forsberg, “Lumped Parameter Model of the Advanced High-Temperature Reactor (AHTR),” American Nuclear Society 2007 Annual Meeting “It’s All About the People: The Future of Nuclear,” June 24–28, 2007, Boston, Massachusetts. Trans. Am. Nucl. Soc , 96, p.795–796 (2007).
H. Akkurt, K. F. Eckerman, J. C. Wagner, and S. Sherbini, “PIMAL: Computational Phantom with Moving Arms and Legs,” American Nuclear Society 2007 Annual Meeting “It’s All About the People: The Future of Nuclear,” June 24–28, 2007, Boston, Massachusetts. Trans. Am. Nucl. Soc. 96, 396–397 (2007).
Bruce Bevard, Gary Mays, Randal Belles, Don Copinger, Barry Oland, and Jy-An Wang, “Updating the Standard Review Plan—An Oak Ridge National Laboratory Perspective,” American Nuclear Society 2007 Annual Meeting “It’s All About the People: The Future of Nuclear,” June 24–28, 2007, Boston, Massachusetts. Trans. Am. Nucl. Soc , 96, p.87–88 (2007).
Charles W. Forsberg, “Accident Criticality Safety for Fast-Spectrum Molten Salt Reactors,” American Nuclear Society 2007 Annual Meeting “It’s All About the People: The Future of Nuclear,” June 24–28, 2007, Boston, Massachusetts. Trans. Am. Nucl. Soc , 96, p.302–303 (2007).
Charles W. Forsberg, “Use of Liquid Salt Coolants to Improve Fast-Reactor Economics,” American Nuclear Society 2007 Annual Meeting “It’s All About the People: The Future of Nuclear,” June 24–28, 2007, Boston, Massachusetts. Trans. Am. Nucl. Soc , 96, p.139–140 (2007).
Charles W. Forsberg and James C. Conklin, “A Nuclear-Fossil Combined-Cycle Power Plan for Base-Load and Peak Electricity,” American Nuclear Society 2007 Annual Meeting “It’s All About the People: The Future of Nuclear,” June 24–28, 2007, Boston, Massachusetts. Trans. Am. Nucl. Soc , 96, p.683–684 (2007).
L. Leal, R. Westfall, D. Eghbali, and F. Trumble, “Assessment of Titanium Cross Sections and Uncertainties for Application in Criticality Safety,” p. 50–52 in Proceedings of the 8th International Conference on Nuclear Criticality Safety (ICNC 2007), Vol. II, May 28–June 1, 2007, St. Petersburg, Russia.
Stephen M. Bowman, Mark D. DeHart, Michael E. Dunn, Sedat Goluoglu, James E. Horwedel, Lester M. Petrie, Jr., Bradley T. Rearden, and Mark L. Williams, “New Criticality Safety Analysis Capabilities in SCALE 5.1,” p. 403–407 in Proceedings of the 8th International Conference on Nuclear Criticality Safety (ICNC 2007), Vol. I, May 28–June 1, 2007, St. Petersburg, Russia.
Stephen M. Bowman, Bradley T. Rearden, and James E. Horwedel, “GeeWiz Integrated Visualization Interface for SCALE 5.1,” p. 12–16 in Proceedings of the 8th International Conference on Nuclear Criticality Safety (ICNC 2007), Vol. II, May 28–June 1, 2007, St. Petersburg, Russia.

D. E. Mueller and J. C. Wagner, “Application of sensitivity/uncertainty methods to burnup credit validation,” Proc. of International Atomic Energy Agency Technical Meeting “Advances in Applications of Burnup Credit to Enhance Spent Fuel Transportation, Storage, Reprocessing and Disposition,” August 29–September 2, 2005, London, United Kingdom.  IAEA-TECDOC-CD-1547, Session 2.2, pg. 183–195 (May 2007).

M. D. DeHart and S. M. Bowman, “Improved radiochemical assay analyses using TRITON depletion sequences in SCALE,” Proc. of International Atomic Energy Agency Technical Meeting “Advances in Applications of Burnup Credit to Enhance Spent Fuel Transportation, Storage, Reprocessing and Disposition,” August 29–September 2, 2005, London, United Kingdom.  IAEA-TECDOC-CD-1547, Session 2, pg. 99–108 (May 2007).

C. V. Parks, C. J. Withee, and J. C. Wagner, “U. S. regulatory recommendations for actinide-only burnup credit in transport and storage casks,” Proc. of International Atomic Energy Agency Technical Meeting “Advances in Applications of Burnup Credit to Enhance Spent Fuel Transportation, Storage, Reprocessing and Disposition,” August 29–September 2, 2005, London, United Kingdom.  IAEA-TECDOC-CD-1547, Session 2.6, pg. 391–399 (May 2007).

J. C. Wagner, C. V. Parks, and D. E. Mueller, “Assessment of benefits for extended burnup credit in transporting PWR spent nuclear fuel in the United States of America,” Proc. of International Atomic Energy Agency Technical Meeting “ Advances in Applications of Burnup Credit to Enhance Spent Fuel Transportation, Storage, Reprocessing and Disposition,” August 29– September 2, 2005, London, United Kingdom .  IAEA-TECDOC-CD-1547, Session 2.5, pg. 347–356 (May 2007).

C. V. Parks and J. C. Wagner, “A coordinated U. S. program to address full burnup credit in transport and storage casks,” in Proc. of International Atomic Energy Agency Technical Meeting “Advances in Applications of Burnup Credit to Enhance Spent Fuel Transportation, Storage, Reprocessing and Disposition,” August 29–September 2, 2005, London, United Kingdom.  IAEA-TECDOC-CD-1547, Session 2, pg. 87–98 (May 2007).

Charles W. Forsberg, Per F. Peterson, and Haihua Zhao, “High-Temperature Liquid-Fluoride-Salt Closed-Brayton-Cycle Solar Power Tower,” J. Sol. Energy Eng., Vol. 129, May 2007, pp. 141–146.

C. W. Forsberg, “The Nuclear-Hydrogen Renewables Economy,” paper submitted to 2 nd Energy Center Hydrogen Initiative Symposium,” April 12–13, 2007, West Lafayette, Indiana.

C. W. Forsberg, S. Rosenbloom, and R. Black, “Producing ethanol from corn using nuclear-generated steam,” Nuclear News, 50, No. 3, 67–69 (March 2007).

C. W. Forsberg, “Future Hydrogen Markets for Large-Scale Hydrogen Production Systems,” International Journal of Hydrogen Energy , 32 (4), pp. 431–439, March 2007.

C. V. Parks, J. C. Wagner, D. E. Mueller, and I. C. Gauld, “Full Burnup Credit in Transport and Storage Casks: Benefits and Implementation,” RadWaste Solutions, Vol. 14, No. 2, March/April 2007, pp. 32–41.

S. M. Bowman, SCALE Newsletter, No. 35, January 2007.


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