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Supercritical Carbon Dioxide Cycle for Next Generation Nuclear Reactors

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Supercritical Carbon Dioxide Cycle for Next Generation Nuclear Reactors ( supercritical-carbon-dioxide-cycle-next-generation-nuclear-r )

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067 see 047 068 069 070 071 072 073 074 PR-075 076 077 078 079 080 081 082 PR-083 Dependency of Human Operator Performance Quality upon Task Complexity, S.J. Automo and M.W. Golay (February 1998). Void Reactivity Performance in Lead-Bismuth-Cooled Reactor for Actinide Transmutation, P. Hejzlar, M.J. Driscoll, and M.S. Kazimi (August 1999). Conceptual Reactor Physics Design of a Lead-Bismuth-Cooled Critical Actinide Burner, P. Hejzlar, M.J. Driscoll, and M.S. Kazimi (February 2000). Physics Benchmark Analysis of the HTR-10 Reactor Using the Monte Carlo Code MCNP, J.R. Lebenhaft and M.J. Driscoll (March 2000). Selection of Correlations and Look-Up Tables for Critical Heat Flux Prediction in the Generation IV ‘IRIS’ Reactor, A. Romano and N.E. Todreas (June 2000). Design of Lead-Bismuth Cooled Reactors for Actinide Burning and for Low Cost Electricity, J. Buongiorno, et al., (June 2000). Analysis of Novel Fuel Geometries for the Generation IV “IRIS” Reactor, A. Romano, and N.E. Todreas (June 2000). Plant Design and Cost Estimation of a Natural Circulation Lead-Bismuth Reactor with Steam Power Conversion Cycle, D. Kim, N.E. Todreas, M.S. Kazimi, and M.J. Driscoll (August 2000). Modular Pebble Bed Reactor Project, Second Annual Progress Report, A.C. Kadak and R.G. Ballinger et al. (July 2000). Plant Design and Cost Estimation of a Natural Circulation Lead-Bismuth Reactor with Helium Power Conversion Cycle, D. Kim, N.E. Todreas, M.S. Kazimi, and M.J. Driscoll (November 2000). Comparison Between Air and Helium for Use as Working Fluids in the Energy-Conversion Cycle of the MPBR, T.A. Galen, D.G. Wilson, and A.C. Kadak (February 2001). The Role of Uncertain Consequences in Nuclear Power Investment Decision Making, L.C. Doboe Jr., N.E. Todreas, and M.W. Golay (September 2000). Conceptual Design of a Lead-Bismuth Cooled Fast Reactor with In-Vessel Direct-Contact Steam Generation, J. Buongiorno, N.E. Todreas, M.S. Kazimi, and K.R. Czerwinski (March 2001). A Review of US Research Activities on Material Compatibility Issues in Nuclear Systems Using Heavy Liquid-Metal Coolant and Needs for Improved Materials, R.G. Ballinger, J.Y. Lim, and M.S. Kazimi (July 2001). Evaluation of a Once-Through Lead-Bismuth-Cooled Reactor Concept, P. Hejzlar, M.J. Driscoll, N.E. Todreas, and M.S. Kazimi (September 2001). Plant Design and Cost Assessment of Forced Circulation Lead-Bismuth Cooled Reactor with Conventional Power Conversion Cycles, V. Dostal, P. Hejzlar, N.E. Todreas, and M.S. Kazimi (September 2001). Design of an Actinide Burning, Lead or Lead-Bismuth Cooled Reactor that Produces Low Cost Electricity, FY 2001 Annual Report, P.E. MacDonald, N.E. Todreas, and J. Buongiourno et al. (October 2001). vi

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