Oak Ridge National Laboratory

Nuclear Modeling, Design, and Safety
2005


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

C. V. Parks and C. M. Hopper, “Technical Basis for Proposed Fissile Exemption Criteria for Transport Packages,” Paper #155 in Proc. of The 14th International Symposium on the Packaging and Transportation of Radioactive Materials (PATRAM 2004), September 20–24, 2004, Berlin, Germany (2005).

C. V. Parks and J. C. Wagner, “Status of Burnup Credit for Transport of SNF in the United States,” Paper #154 in Proc. of The 14th International Symposium on the Packaging and Transportation of Radioactive Materials (PATRAM 2004), September 20–24, 2004, Berlin, Germany (2005).

C. W. Forsberg, P.M. Swaney, and T. N. Tiegs, “Characteristics and Fabrication of Cermet Spent Nuclear Fuel Casks: Ceramic Particles Embedded in Steel,” Paper #290 in Proc. of The 14th International Symposium on the Packaging and Transportation of Radioactive Materials (PATRAM 2004), September 20–24, 2004, Berlin, Germany (2005).

C. W. Forsberg, “Futures for Hydrogen Production Using Nuclear Energy,” Progress in Nuclear Energy, 47 (1–4) 484–495 (2005).

C. W. Forsberg, “The Advanced High-Temperature Reactor: High-Temperature Fuel, Liquid Salt Coolant, and Liquid-Metal Plant,” Progress in Nuclear Energy, 47 (1–4) 32–43 (2005).

R. D. Busch and S. M. Bowman, KENO V.a Primer: A Primer for Criticality Calculations with SCALE/KENO V.a Using GeeWiz, ORNL/TM-2005/135, UT-Battelle, LLC, Oak Ridge National Laboratory, December 2005. [Export Controlled Document published on CD-ROM and distributed by RSICC.]

D. T. Ingersoll, K. T. Clarno, C. W. Forsberg, J. C. Gehin, R. W. Christiansen, C. B. Davis, G. L. Hawkes, J. W. Sterbentz, T. K. Kim, T. A. Taiwo, and W. S. Yang, Status of Physics and Safety Analysis for the Liquid-Salt-Cooled Very High-Temperature Reactor (LS-VHTR), ORNL/TM-2005/218, UT-Battelle, LLC, Oak Ridge National Laboratory, December 2005.

C. W. Forsberg, “The Hydrogen Economy is Coming – The Question is Where?” Chem. Eng. Prog., Vol. 101 (12), 20–22 (December 2005).
Kevin. T. Clarno, Charles W. Forsberg, and Jess C. Gehin, “Physics Analysis of Coolant Voiding in the Advanced High-Temperature Reactor (AHTR),” 2005 ANS Winter Meeting, “Talk About Nuclear Differently: A Good Story Untold,” November 13-17, 2005, Washington, D. C. Trans. Am. Nucl. Soc. 93, 977–980 (November 2005).
C. W. Forsberg, “Nuclear Hydrogen for Production of Liquid Hydrocarbon Transport Fuels,” Paper 581a in Proc. 2005 American Institute of Chemical Engineers Fall Meeting, October 30–November 4, 2005, Cincinnati, OH (October 2005).

S. M. Bowman, B. T. Rearden, and J. E. Horwedel, “ Complete User Visualization Interface for KENO,” stevebowman-1.pdf in Proc. of 2005 NCSD Topical Meeting – Integrating Criticality Safety into the Resurgence of Nuclear Power, September 19–22, 2005, Knoxville, Tennessee, on CD-ROM, American Nuclear Society, LaGrange Park, Illinois (2005).

H. L. Dodds, C. M. Hopper, R. E. Pevey, D. A. Reed, R. G. Taylor, and R. M. Westfall, “Nuclear Criticality Safety Education and Training: Anytime and Anywhere,” hdj-1.pdf in Proc. of 2005 NCSD Topical Meeting – Integrating Criticality Safety into the Resurgence of Nuclear Power, September 19–22, 2005, Knoxville, Tennessee, on CD-ROM, American Nuclear Society, LaGrange Park, Illinois (2005).

C. W. Forsberg, Molten Salt Reactor Critical Systems Evaluations, ORNL/GEN4/LTR-05-005, UT-Battelle, LLC, Oak Ridge National Laboratory, September 15, 2005.

V. Z. Matveev, A. I. Morenko, V. I. Shapovalov, V. V. Shatalov, V. A. Seredenko, V. T. Gotovchikov, A. M. Visik, A. G. Seminov, V. M. Sergeev, and C. W. Forsberg, “Production and Testing of Cask Cermet on the Base of Stainless/Carbon Steel and Depleted Uranium Dioxide as Applied to its Use as Shielding Materials in Constructions of Casks for Spent Nuclear Fuel and Radioactive Wastes,” in Proc. of the 10th International Conference on Environmental Remediation and Radioactive Waste Management (ICEM '05), September 4-8, 2005, Glasgow, Scotland, American Society of Mechanical Engineers (September 2005).
V. T. Gotovchikov, V. A. Seredenko, V. V. Shatalov, V. V. Shilov, B. S. Mironov, and C. W. Forsberg, “Use of an Induction Cold Crucible Melter to Manufacture Depleted Uranium Dioxide (DUO 2) Particles for Use in Spent Nuclear Fuel Casks” in Proc. of the 10th International Conference on Environmental Remediation and Radioactive Waste Management (ICEM '05), September 4-8, 2005, Glasgow, Scotland, American Society of Mechanical Engineers (September 2005).

C. W. Forsberg, T. N. Tiegs, and V. K. Sikka, “Powder-Metallurgy Experiments and Manufacturing Studies of DUO2 -Steel Cermets for Spent Nuclear Fuel Casks” Paper ICEM05-1350 in Proc. of the 10th International Conference on Environmental Remediation and Radioactive Waste Management (ICEM '05), September 4-8, 2005, Glasgow, Scotland, American Society of Mechanical Engineers (September 2005).

R. J. Belles, B. B. Bevard, J. J. Carbajo, and J. C. Gehin, ORNL Fissile Material Disposition Program: FY05 Programmatic, Technical, and Financial Report on the State of the VVER-1000 Project,ORNL/MD/LTR-286, UT-Battelle, LLC, Oak Ridge National Laboratory, August 2005.

S. M. Bowman, SCALE Newsletter, No. 32, July 2005.
B. Yildiz, M. C. Petri, G. Conzelmann, and C. W. Forsberg, Configuration and Technology Implications of Potential Nuclear Hydrogen System Applications, ANL-05/30, Argonne National Laboratory, July 31, 2005.

D. F. Williams, L. M. Toth, K. T. Clarno, and C. W. Forsberg, Assessment of Properties of Candidate Liquid Salt Coolants for the Advanced High-Temperature Reactor (AHTR), ORNL/GEN4/LTR-05-001, UT-Battelle, LLC, Oak Ridge National Laboratory, June 30, 2005.

C. W. Forsberg, T. D. Burchell, D. F. Williams D. E. Holcomb, R. F. Holdaway, and A. L. Qualls, “Carbon-Carbon-Composite Salt-Cooled Electric Space Reactors,” Paper 1148, pp. 54–61 in Proc. of the Space Nuclear Conference 2005 (SNC’05); Embedded Topical Meeting in the 2005 ANS Annual Meeting, June 5–9, 2005, San Diego, California.

 C. W. Forsberg, “Brayton Power Cycles and High-Temperature Salt-Cooled Reactors,” 2005 ANS Annual Meeting, “The Next 50 Years: Creating Opportunities,” June 5–9, 2005, San Diego, California. Trans. Am. Nucl. Soc. 92, 231–233 (2005).

J. T. Thomas, R. M. Westfall, and C. M. Hopper, “History of the Oak Ridge Critical Experiments Program,” 2005 ANS Annual Meeting, “The Next 50 Years: Creating Opportunities,” June 5–9, 2005, San Diego, California. Trans. Am. Nucl. Soc. 92, 470-471 (2005).

D. Loaiza, R. Sanchez, K. Chesson, R. M. Westfall, and C. Hopper, “Critical Mass Experiment with Niobium – 1 wt % Zirconium Fueled with Highly Enriched Uranium in Support of Project Prometheus,” 2005 ANS Annual Meeting, “The Next 50 Years: Creating Opportunities,” June 5-9, 2005, San Diego, California. Trans. Am. Nucl. Soc. 92, 580-581 (2005).

S. M. Bowman and J. E. Horwedel, “GeeWiz: Integrated User Interface for SCALE,” 2005 ANS Annual Meeting, “The Next 50 Years: Creating Opportunities,” June 5–9, 2005, San Diego, California. Trans. Am. Nucl. Soc. 92, 767-769 (2005).

S. M. Bowman, “Overview of Advances in SCALE Development,” 2005 ANS Annual Meeting, “The Next 50 Years: Creating Opportunities,” June 5–9, 2005, San Diego, California. Trans. Am. Nucl. Soc .92, 747–748 (2005).

C. W. Forsberg and K. T. Clarno, “The Advanced High-Temperature Reactor (AHTR): Flux Distribution and Dosimetry,” Twelfth International Symposium on Reactor Dosimetry, May 8–13, 2005, Gatlinburg, TN, to be published in J. of ASTM International, ASTM, West Conshohocken, PA (in press).

C. W. Forsberg , P. F. Peterson , and D. F. Williams, “ Liquid-Salt-Cooling for Advanced High-Temperature Reactors,” Paper 5401 in Proc. of 2005 International Conference on Advances in Nuclear Power Plants (ICAPP ’05), May 15–19, 2005, Seoul, Korea, American Nuclear Society (May 2005).

C. W. Forsberg , P. F. Peterson, and D. F. Williams, “ Practical Aspects of Liquid-Salt-Cooled Fast-Neutron Reactors,” Paper 5643 in Proc. of 2005 International Conference on Advances in Nuclear Power Plants (ICAPP ’05), May 15–19, 2005, Seoul, Korea, American Nuclear Society (May 2005).

SCALE:  A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluations, ORNL/TM-2005/39, Version 5, Vols. I–III, April 2005.  Available from Radiation Safety Information Computational Center at Oak Ridge National Laboratory as CCC-725.

S. M. Bowman, M. D. DeHart, and L. M. Petrie, “ Integrated KENO Monte Carlo Transport for 3-D Depletion with SCALE,” usr-stevebowman-1-paper.pdf in Proc. of The Monte Carlo 2005 Topical Meeting, The Monte Carlo Method: Versatility Unbounded in a Dynamic Computing World, April 17–21, 2005, Chattanooga, Tennessee, on CD-ROM, American Nuclear Society, La Grange Park, Illinois (2005).

S. M. Bowman, B. T. Rearden, and J. E. Horwedel, “Integrated Interactive Visualization for KENO,” usr-stevebowman-2-paper.pdf in Proc. of The Monte Carlo 2005 Topical Meeting, The Monte Carlo Method: Versatility Unbounded in a Dynamic Computing World, April 17–21, 2005, Chattanooga, Tennessee, on CD-ROM, American Nuclear Society, La Grange Park, Illinois (2005).

C. W. Forsberg, “Hydrogen Markets: Implications for Hydrogen Production Technologies,” Paper 73e in Proc. of 2005 AIChE Spring National Meeting, April 10–14, 2005, Atlanta, Georgia (April 2005).

C. W. Forsberg, “Hydrogen, Liquid Fuels, and R. E. Wilson,”2005 AIChE Spring National Meeting, April 10–14, 2005, Atlanta, Georgia (Speech for Award Banquet to be Published in American Institute of Chemical Engineers Newsletter). (In Press).

C. W. Forsberg, “ The Longer-Term Option: The Advanced High-Temperature Reactor,” Proc of The Next Generation Nuclear Plant Goals and Challenges, Center of Advanced Nuclear Energy Systems, Massachusetts Institute of Technology, February 23–24, 2005, Cambridge, Massachusetts (February 2005).

D. T. Ingersoll, E. J. Parma, C. W. Forsberg, and J. P. Renier, “Core Physics Characteristics and Issues for the Advanced High-Temperature Reactor (AHTR) Concept,Workshop on Advanced Reactors with Innovative Fuels (ARWIF-2005), February 16–18, 2005, Oak Ridge, TN, Nuclear Science Committee, OECD Nuclear Energy Agency, Paris, France (in press).

C. W. Forsberg, “Future Directions: Toward Higher-Temperature Reactors,” Workshop on Advanced Reactors with Innovative Fuels (ARWIF-2005), February 16–18, 2005, Oak Ridge, TN, Nuclear Science Committee, OECD Nuclear Energy Agency, Paris, France (in press).

C. W. Forsberg, Nuclear Hydrogen for Peak Electricity Production and Spinning Reserve, ORNL/TM-2004/194, UT-Battelle, LLC, Oak Ridge National Laboratory, January 2005.

C. W. Forsberg, “What is the Initial Market for Hydrogen from Nuclear Energy?” American Nuclear Society. Nuclear News, 48 (1), 24-26 (January 2005).

S. M. Bowman , SCALE Newsletter, No. 31, January 2005.


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