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2004 Publications


C. W. Forsberg, “Lowering Peak Temperatures for Nuclear Thermochemical Production of Hydrogen,” Second International Symposium on Safety and Economy of Hydrogen Transport, Town of Sarov, Nizhniy Novgorod Region, Russia, August 18-21, 2003, published in International Scientific Journal of Alternative Energy and Ecology, 3 (11), 11-19 (2004).

G. E. Whitesides, R. M. Westfall, and C. M. Hopper, “Criticality Safety Methods,” book chapter submitted to Kluwer Academic Publishers, N.Y., 2004 (In press).

C. W. Forsberg, “Production of Hydrogen Using Nuclear Energy,” Second International Symposium on Safety and Economy of Hydrogen Transport, Town of Sarov, Nizhniy Novgorod Region, Russia, August 18-21, 2003, published in International Scientific Journal for Alternative Energy and Ecology, 2: (10), 5-9(2004).

B. L. Broadhead et al., “Sensitivity-and-Uncertainty-Based Criticality Safety Validation Techniques,” Nucl. Sci. Eng. 146, 340-366 (2004).

C. W. Forsberg, P. F. Peterson, and H. Zhao, “Sustainability, Water, Dry Cooling, and the Advanced High-Temperature Reactor,” 2004 ANS Winter Meeting: "Leadership Toward a Progressive, Integrated Nuclear Community - Going Forward Together," Washington, D. C., November 14-18, 2004, Trans. Am. Nucl. Soc. 91, 415-417 (2004).

C. W. Forsberg, “Nuclear Hydrogen for Peak Electricity Production and Commercial Sale,” 2004 ANS Winter Meeting: "Leadership Toward a Progressive, Integrated Nuclear Community - Going Forward Together,"Washington, D. C., November 14-18, 2004, Trans. Am. Nucl. Soc. 91, 103-104 (2004).

C. W. Forsberg, E. D. Collins, C. W. Alexander, and J. P. Renier, “Can Thermal Reactor Recycle Eliminate the Need for Multiple Recycle?” Proc. Actinide and Fission Product Partitioning and Transmutation: 8th Information Exchange Meeting, Las Vegas, Nev., November 9-11, 2004, OECD Nuclear Energy Agency, Paris, France (2004).

C. V. Parks, Report of Foreign Travel to Berlin, Germany, and Vienna, Austria, September 19-October 1, 2004, FTR XA 215001, October 2004.

C. W. Forsberg, “The Advanced High-Temperature Reactor: High-Temperature Fuel, Molten Salt Coolant, and Liquid-Metal Plant,” Proc. The 1st COE-INIES International Symposium (INIES-1), Tokyo Institute of Japan, Tokyo, Japan, October 31-November 4, 2004.

C. W. Forsberg, “Futures for Hydrogen Production Using Nuclear Energy,” Proc. The 1st COE-INIES International Symposium (INIES-1), Tokyo Institute of Japan, Tokyo, Japan, October 31-November 4, 2004.

C. W. Forsberg, P. F. Peterson, and L. Ott, “The Advanced High-Temperature Reactor (AHTR) for Producing Hydrogen to Manufacture Liquid Fuels,” Proc. 2004 Americas Nuclear Energy Symposium, Miami Beach, Fla., October 3-6, 2004, American Nuclear Society, La Grange Park, Ill. .

M. J. Haire, C. W. Forsberg, V. Z. Matveev, and V. I. Shapovalov, “Characteristics of Next-Generation Spent Nuclear Fuel (SNF) Transport and Storage Casks,” Proc. 2004 Americas Nuclear Energy Symposium, Miami Beach, Fla., October 3-6, 2004, American Nuclear Society, La Grange Park, Ill .

R. M. Westfall and R. D. McKnight, "Nuclear Data Activities in Support of the DOE Nuclear Safety Program," Proc. International Conference on Nuclear Data for Science and Technology, Santa Fe, N. Mex., September 26-October 1, 2004.

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

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

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

S. J. Ball and C. W. Forsberg, “Advanced High-Temperature Reactor (AHTR) Loss-of-Forced Circulation Accidents,” Proc. 2nd International Topical Meeting on High-Temperature Reactor Technology (HTR2004), Beijing, China, September 20-24, 2004, International Atomic Energy Agency, Vienna, Austria (September 2004).

C. W. Forsberg, "Reactors with Molten Salts: Options and Missions," The 2004 Frederic Joliot & Otto Han Summer School on Nuclear Reactors: Physics, Fuels, and Systems, Cadarache, France, August 25-September 3, 2004. Published on CD-ROM .

S. M. Bowman, SCALE Newsletter, No. 30, July 2004.

C. W. Forsberg, P. F. Peterson, and H. Zhao, “An Advanced Molten Salt Reactor Using High-Temperature Reactor Technology,” Proc. 2004 International Congress on Advances in Nuclear Power Plants (ICAPP’04), Embedded Topical: 2004 American Nuclear Society Annual Meeting, Pittsburgh, Pa., June 13-17, 2004, American Nuclear Society, La Grange Park, Ill.

B. L. Bischoff, L. D. Trowbridge, L. K. Mansur, and C. W. Forsberg, “Production of Hydrogen Using Nuclear Energy and Inorganic Membranes,” Proc. 2004 International Congress on Advances in Nuclear Power Plants (ICAPP’04), Embedded Topical: 2004 American Nuclear Society Annual Meeting, Pittsburgh, Pa., June 13-17, 2004, American Nuclear Society, La Grange Park, Ill.

C. W. Forsberg, P. F. Peterson, and P. Pickard, “Maximizing Temperatures of Delivered Heat From the Advanced High-Temperature Reactor,” Proc. 2004 International Congress on Advances in Nuclear Power Plants (ICAPP’04), Embedded Topical: 2004 American Nuclear Society Annual Meeting, Pittsburgh, Pa., June 13-17, 2004, American Nuclear Society, La Grange Park, Ill. (June 2004).

C. W. Forsberg, “A Multifunction Cask for Spent Fuel At-Reactor Storage of Short-Cooled Fuel, Transport, and Disposal,” Proc. 2004 International Congress on Advances in Nuclear Power Plants ( ICAPP’04), Embedded Topical: 2004 American Nuclear Society Annual Meeting, Pittsburgh, Pa., June 13-17, 2004, American Nuclear Society, La Grange Park, Ill. (June 2004) .

C. W. Forsberg, "Safety and Licensing Aspects of the Molten Salt Reactor," 2004 American Nuclear Society Annual Meeting, Pittsburgh, Pa., June 13-17, 2004, Trans. Am. Nucl. Soc., 90, 27-29 (June 2004).

C. W. Forsberg and M. A. Feltus, "Fuel Requirements for the Advanced High-Temperature Reactor: Graphite Coated-Particle Fuel and Molten Fluoride Salt Coolant," Technical Meeting on Current Status and Future Prospects of Gas-Cooled Reactor Fuels, Vienna, Austria, June 7-9, 2004.

D. T. Ingersoll et al., Status of Preconceptual Design of the Advanced High-Temperature Reactor (AHTR), ORNL/TM-2004/104, UT-Battelle, LLC, Oak Ridge National Laboratory, Oak Ridge, Tenn., May 2004.

R. M. Westfall and C. M. Hopper, Joint Report of Foreign Travel to Paris, April 9-19, 2004, FTR XA 208273 and 208472, May 2004.

C. W. Forsberg, "A Multifunction Cask for At-Reactor Storage of Short-Cooled Spent Fuel, Transport, and Disposal," Proc. of International Topical Meeting on Advanced Nuclear Installation Safety, San Francisco, Calif., May 2-6, 2004.

C. V. Parks, Report of Foreign Travel to Paris, France, and Berlin, Germany, March 13-20, 2004, FTR XA 207620, April 2004.

C. W. Forsberg, L. D. Trowbridge, B. B. Bischoff, and L. K. Mansur, “Sulfur Thermochemical Processes With Inorganic Membranes to Produce Hydrogen," Proc. of Third Topical Conference on Fuel Cell Technology, Embedded Conference in the American Institute of Chemical Engineers 2004 Spring Meeting, New Orleans, La., April 25-29, 2004, American Institute of Chemical Engineers, N.Y. (2004).

C. W. Forsberg and V. Likka, "A New Method for Manufacturing Depleted Uranium Dioxide-Steel Cermet Cask for Spent Nuclear Fuel and Radioactive Wastes," Processing of Specialty Metals: Emphasis on Depleted Uranium, April 20-22, 2004, Oak Ridge, Tenn., American Society of Manufacturing (April 2004).

C. V. Parks and J. C. Wagner, "Current Status and Potential Benefits of Burnup Credit for Spent Fuel Transportation," Proc. of 14th Pacific Basin Nuclear Conference, Honolulu, Hawaii, March 21-25, 2004, American Nuclear Society, La Grange Park, Ill. (March 2004)

C. W. Forsberg, "A Large Low-Pressure Advanced High-Temperature (AHTR)," Proc. of 14th Pacific Basin Nuclear Conference, Honolulu, Hawaii, March 21-25, 2004, American Nuclear Society, La Grange Park, Ill. (March 2004)

S. M. Bowman, SCALE Newsletter, No. 29, January 2004.

 

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