Optimized Core Design of a Supercritical Carbon Dioxide-Cooled Fast Reactor
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Michael J. Driscoll | Pavel Hejzlar | Christopher S. Handwerk | M. Driscoll | P. Hejzlar | C. Handwerk
[1] Vaclav Dostal,et al. A Supercritical CO{sub 2} Cycle- a Promising Power Conversion System for Generation IV Reactors , 2006 .
[2] R. Moore,et al. Behaviour of BeO under neutron irradiation , 1964 .
[3] M. J. Driscoll,et al. ASSESSMENT OF GAS COOLED FAST REACTOR WITH INDIRECT SUPERCRITICAL CO 2 CYCLE , 2006 .
[4] K. H. Sarma,et al. New processing methods to produce silicon carbide and beryllium oxide inert matrix and enhanced thermal conductivity oxide fuels , 2006 .
[5] C. Degueldre,et al. Thermal conductivity of zirconia based inert matrix fuel: use and abuse of the formal models for testing new experimental data , 2003 .
[6] E. Ruckenstein,et al. The characterization of a highly effective NiO/MgO solid solution catalyst in the CO2 reforming of CH4 , 1997 .
[7] D. Wade,et al. The Integral Fast Reactor Concept: Physics of Operation and Safety , 1988 .
[8] Dennis Ross Poulter. Nuclear Engineering. (Book Reviews: The Design of Gas-Cooled Graphite-Moderated Reactors) , 1963 .
[9] J. Collier,et al. Gas-cooled Fast Reactor , 1968, Nature.
[10] C. E. Till,et al. Integral Fast Reactor concept , 1986 .
[11] F. Illas,et al. Ab Initio Cluster Model Calculations on the Chemisorption of CO2 and SO2 Probe Molecules on MgO and CaO (100) Surfaces. A Theoretical Measure of Oxide Basicity , 1994 .
[12] C. P. Gratton. The GCFR revisited , 2003 .
[13] H. P. Planchon,et al. Implications of the EBR-II inherent safety demonstration test☆ , 1987 .
[14] Timothy Abram,et al. A Technology Roadmap for Generation-IV Nuclear Energy Systems, USDOE/GIF-002-00 , 2002 .
[15] Zhiwen Xu,et al. Design strategies for optimizing high burnup fuel in pressurized water reactors , 2003 .
[16] R. Campana,et al. Irradiation testing of design models for the GCFR fuel pressure equalization (vent) system , 1974 .
[17] R. Konings,et al. On the thermal conductivity of inert-matrix fuels containing americium oxide , 1998 .
[18] M. Driscoll,et al. The Linear Reactivity Model for Nuclear Fuel Management , 1991 .
[19] Nathan Carstens. Speedup of MCNP(X) parallel KCODE execution via communication algorithm development and Beowulf Cluster optimization , 2004 .
[20] B. S. Hickman,et al. The effect of neutron irradiation on beryllium oxide , 1964 .
[21] Neil E. Todreas,et al. Conceptual Design of a Large, Passive Pressure-Tube Light Water Reactor , 1994 .
[22] Vaclav Dostal,et al. High-Performance Supercritical Carbon Dioxide Cycle for Next-Generation Nuclear Reactors , 2006 .
[23] K. Kawashima,et al. Utilization of fast reactor excess neutrons for burning long lived fission products , 1995 .
[24] P. Medvedev,et al. Development of dual phase magnesia-zirconia ceramics for light water reactor inert matrix fuel , 2005 .
[25] Claude Degueldre,et al. Thermophysical Properties of Inert Matrix Fuels for Actinide Transmutation. , 2003 .
[26] M. J. Driscoll,et al. Optimized, Competitive Supercritical-CO2 Cycle GFR for Gen IV Service , 2008 .
[27] Neil E. Todreas,et al. Fertile-Free Fast Lead-Cooled Incinerators for Efficient Actinide Burning , 2004 .
[28] N. Todreas,et al. Hydrodynamic models and correlations for bare and wire-wrapped hexagonal rod bundles — Bundle friction factors, subchannel friction factors and mixing parameters , 1986 .
[29] M. Driscoll,et al. An advanced vented fuel assembly design for GFR applications , 2005 .
[30] Mujid S. Kazimi,et al. High Performance Fuel Design for Next Generation PWRs: Final Report , 2006 .
[31] George E. Apostolakis,et al. Risk-informed design guidance for future reactor systems , 2005 .