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PR-084 Modular Pebble Bed Reactor Project: Third Annual Report, A.C. Kadak and R.G. Ballinger et al. (November 2001). 085 Power Conversion Cycle Selection for the LBE Cooled Reactor with Forced Circulation, V. Dostal, N.E. Todreas, P. Hejzlar, and M.S. Kazimi (February 2002). 086 Neutronic Evaluation of GCFR Core Diluents, K. Yu, M.J. Driscoll, and P. Hejzlar (June 2003). 087 Modern Gas-Cooled Fast Reactor Safety Assurance Considerations, M.J. Driscoll, P. Hejzlar, N.E. Todreas, and B. Veto (May 2003). 088 Thermal Hydraulics and Shutdown Cooling of Supercritical CO2 GT-GCFRs, Y. Okano, P. Hejzlar, N.E. Todreas, and M.J. Driscoll (August 2002). 089 Deterministic Casuality Analysis of the Pebble Bed Modular Reactor for use with Risk-Based Safety Regulation, J.E. Withee and M.W. Golay (August 2002). 090 CO2 Brayton Cycle Design and Optimization, V. Dostal, M.J. Driscoll, P. Hejzlar, and N.E. Todreas (November 2002). 091 Component Design and Capital Cost Analysis of a Forced Circulation Lead-Bismuth Eutectic Cooled Nuclear Reactor, R. Herron, N.E. Todreas, and P. Hejzlar (February 2003). PR-092 Design of an Actinide Burning, Lead or Lead-Bismuth Cooled Reactor That Produces the Low Cost Electricity, FY-02 Annual Report, P.E. MacDonald, N.E. Todreas, and J. Buongiourno et al. (October 2002). PR-093 Development of Gen IV Advanced Gas-Cooled Reactors with Hardened/Fast Neutron Sprectrum, Annual Progress Report, M.J. Driscoll, P. Hejzlar, N.E. Todreas, Y. Okano, V. Dostal, and K. Yu (September 2002). PR-094 Modular Pebble Bed Reactor Project: Fourth Annual Report, A.C. Kadak and R.G. Ballinger et al. (December 2002). 095 Analysis of a Convection Loop for GFR Post – LOCA Decay Heat Removal from a Block-Type Core, W. Williams, P. Hejzlar, M.J. Driscoll, W-J. Lee, and P. Saha (March 2003). 096 A Tight Lattice, Epithermal Core Design for the IRIS Reactor, J.G.B. Saccheri and N.E. Todreas (May 2003). 097 A Tight Lattice, Epithermal Core Design for the Integral PWR, J.G.B. Saccheri, N.E. Todreas, and M.J. Driscoll (August 2003). 098 Thermal Hydraulic Design of Hydride Fueled Pressurized Water Reactor Cores, J.A. Malen and N.E. Todreas (to be published). 099 Thermal Hydraulic Performance Analysis of a Small Integral Pressurized Water Reactor Core, S. Blair and N.E. Todreas (to be published). 100 A Supercritical Carbon Dioxide Cycle for Next Generation Nuclear Reactors, V. Dostal, M.J. Driscoll, P. Hejzlar, March 2004 viiPDF Image | Supercritical Carbon Dioxide Cycle for Next Generation Nuclear Reactors
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