Reactor and Nuclear Systems Division

Reactor and Nuclear Systems Division
2007 Publications

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

L. R. Dole et al., "Carbonate Thermochemical Cycle for the Production of Hydrogen," DOE Solar-Thermal Water Splitting Program Review Meeting, Denver, Colo., November 15-16, 2007.

R. J. Ellis, "Prospects of Using Reprocessed Uranium in CANDU Reactors, in the U.S. GNEP Program," Proc. of The American Nuclear Society and the European Nuclear Society 2007 International Conference on Making the Renaissance Real, Washington, D.C., November 11-15, 2007, Trans. Am. Nucl. Soc. 97, 107-108 (2007).

S. Goluoglu, S. M. Bowman, and M. E. Dunn, “KENO Monte Carlo Code Capabilities,” Proc. of The American Nuclear Society and the European Nuclear Society 2007 International Conference on Making the Renaissance Real, Washington, D.C., November 11-15, 2007, Trans. Am. Nucl. Soc. 97, 592–594 (2007).

S. M. Bowman, “Overview of the SCALE Code System,” Proc. of The American Nuclear Society and the European Nuclear Society 2007 International Conference on Making the Renaissance Real, Washington, D.C., November 11-15, 2007, 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,” Proc. of The American Nuclear Society and the European Nuclear Society 2007 International Conference on Making the Renaissance Real, Washington, D.C., November 11-15, 2007, Trans. Am. Nucl. Soc. 97, 606–607 (2007).

L. D. Trowbridge, J.-P. Renier, and G. D. DelCul, "Evaluation of Reuse of Reprocessed Uranium in the Context of the U.S. Global Nuclear Energy Partnership Program," Proc. of the American Nuclear Society and the European Nuclear Society 2007 International Conference on Making the Renaissance Real, Washington, D.C., November 11-15, 2007, Trans. Am. Nucl. Soc. 97, 105-106 (2007).

T. Uckan, Implementation of the Fissile Mass Flow Monitor Source Verification and Confirmation, ORNL/TM-2077/068, Oak Ridge National Laboratory, Oak Ridge, Tenn., December 2007.

C. W. Forsberg, “Changing Biomass, Fossil, and Nuclear Fuel Cycles for Sustainability,” Proc. of 2007 AIChE Annual Meeting, Salt Lake City, Utah, November 4–9, 2007.

C. W. Forsberg, “Meeting U.S. Liquid Transport Fuel Needs with a Nuclear Hydrogen Biomass System,” Proc. of 2007 AIChE Annual Meeting, Salt Lake City, Utah, November 4–9, 2007.

C. W. Forsberg and M. B. Gorensek, “Relative Economic Incentives for Hydrogen from Nuclear, Renewable, and Fossil Energy Sources,” Proc. of 2007 AIChE Annual Meeting, Salt Lake City, Utah, November 4–9, 2007.

M. F. Cunningham et al., "Active-Mask Coded-Aperture Imaging," Proc. IEEE, Honolulu, Hawaii, October 31-November 4, 2007.

C. W. Forsberg and J. 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, Oak Ridge, Tenn., September 2007.

C. Myers, B. L. Kirk, and L. C. Leal, "Comparative Analysis of Nuclear Cross Sections in Monte Carlo Methods for Medical Physics Applications," Proc. of the Computational Medical Physics Working Group Workshop II, Gainesville, Fla., September 30 – October 3, 2007, on CD-ROM.

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

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

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

M. J. Haire and C. W. Forsberg, “Tags to Track Illicit Uranium and Plutonium,” Proc. of Global 2007: Advanced Nuclear Fuel Cycles and Systems, Boise, Idaho, September 9–13, 2007, American Nuclear Society, La Grange Park, Ill.

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.

D. Wiarda and M. E. Dunn, "Updated Covariance Processing Capabilities in the AMPX Code System," Proc. of the Eighth International Topical Meeting on Nuclear Applications and Utilization of Accelerators, Pocatello, Idaho, July 30-August 2, 2007.

M. W. Wendel, A. A. Abdou, B. Riemer, and D. K. Felde, "Gas Bubble Formation in Stagnant and Flowing Mercury," Proc. of the 5th Joint ASME/JSME Fluids Engineering, San Diego, Calif., July 30-August 2, 2007.

A. A. Abdou, D. K. Felde, B. Riemer, and M. W. Wendel, "CFD Validation of Gas Injection into Stagnant Water," Proc. of the 5th Joint ASME/JSME Fluids Engineering, San Diego, Calif., July 30-August 2, 2007.

H. Akkurt et al., “Development of a Computational Phantom with Moving Arms and Legs for Radiation Dose Assessment,”52nd Annual Meeting of the Health Physics Society, Portland, Oreg., July 8–12, 2007.

J. J. Carbajo, G. L. Yoder, and C. 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,”Boston, Mass., June 24–28, 2007, Trans. Am. Nucl. Soc. 96, p.797–799 (2007).

J. J. Carbajo, G. L. Yoder, and C. 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,”Boston, Mass., June 24–28, 2007, 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,” Boston, Mass., June 24–28, 2007, Trans. Am. Nucl. Soc. 96, 396–397 (2007).

B. B. Bevard et al., “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,” Boston, Mass., June 24–28, 2007, Trans. Am. Nucl. Soc. 96, p.87–88 (2007).

C. 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,” Boston, Mass., June 24–28, 2007, Trans. Am. Nucl. Soc. 96, p.302–303 (2007).

C. 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,”Boston, Mass., June 24–28, 2007, Trans. Am. Nucl. Soc. 96, p.139–140 (2007).

C. W. Forsberg and J. 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,” Boston, Mass., June 24–28, 2007, Trans. Am. Nucl. Soc. 96, p.683–684 (2007).

L. R. Dole and C. H. Mattus, "Low pH Concrete and Grout for Use in the US High-Level Waste Repository: Part I," R&D on Low-pH Cement for a Geological Repository, 3rd Workshop, Paris, France, June 13-14, 2007.

J. J. Carbajo and A. L. Qualls, "Modeling and Analysis of a Lunar Space Reactor with the Computer Code RELAP5 – 3D/ATHENA," Proc. of the Embedded Topical Meeting:  2008 International Congress Advances in Nuclear Power Plants (ICAPP’08), Anaheim, Calif., June 8-12, 2007.

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,” London, U.K., August 29–September 2, 2005. 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,” London, U.K., August 29–September 2, 2005.  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,” London, U.K., August 29–September 2, 2005.  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,” London, U.K., August 29–September 2, 2005.  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,” Proc. of International Atomic Energy Agency Technical Meeting “Advances in Applications of Burnup Credit to Enhance Spent Fuel Transportation, Storage, Reprocessing and Disposition,” London, U.K., August 29–September 2, 2005.  IAEA-TECDOC-CD-1547, Session 2, pp.87–98 (May 2007).

C. W. Forsberg, P. F. Peterson, and H. Zhao, “High-Temperature Liquid-Fluoride-Salt Closed-Brayton-Cycle Solar Power Tower,” J. Sol. Energy Eng. 129, 141–146 (May 2007).

L. Leal, R. Westfall, D. Eghbali, and F. Trumble, “Assessment of Titanium Cross Sections and Uncertainties for Application in Criticality Safety,” Proc. of the 8th International Conference on Nuclear Criticality Safety (ICNC 2007), Vol. II, St. Petersburg, Russia, May 28–June 1, 2007.

S. M. Bowman et al., “New Criticality Safety Analysis Capabilities in SCALE 5.1,” Proc. of the 8th International Conference on Nuclear Criticality Safety (ICNC 2007), Vol. I, St. Petersburg, Russia, May 28–June 1, 2007.

S. M. Bowman, B. T. Rearden, and J. E. Horwedel, “GeeWiz Integrated Visualization Interface for SCALE 5.1,” Proc. of the 8th International Conference on Nuclear Criticality Safety (ICNC 2007), Vol. II, St. Petersburg, Russia, May 28–June 1, 2007.

N. M. Larson et al., "Current Status of the R-Matrix Code SAMMY, with Emphasis on the Relationship," Proc. of the International Conference on Nuclear Data for Science and Technology (ND-2007), Vol. 1, Nice, France, April 22-27, 2007.

B. L. Kirk, "A review of RSICC software for medical and health physics", Proc. of the International Conference on Nuclear Data for Science and Technology (ND-2007), Nice, France, April 22-27, 2007.

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

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.