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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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032 A Strategy for Extending Cycle Length to Improve Pressurized Water Reactor Capacity Factor, A.F.A. Ayoub and M.J. Driscoll (June 1995). 033 Conception and Experimental Investigation of Thermal Switches, J. Novak, N.E. Todreas, and M.J. Driscoll (June 1995). 034 Alternative Passive Cooling Concepts for a Large Rating Pressurized Water Reactor Containment, M. Gavrilas, N.E. Todreas, and M.J. Driscoll (August 1995). 035 An Integrated Formal Approach for Developing High Quality Software for Safety-Critical Systems, M. Ouyang and M.W. Golay (September 1995). 036 Surveillance Strategy for a Four-Year Operating Cycle in Commercial Nuclear Reactors, T.J. Moore, J.H. Maurer, R.S. McHenry, and N.E. Todreas (June 1996). 037 The Performance Study of the Tube Water Wall PCCL and an Experimental Correlation for Steam Condensation in the Presence of Air Under Natural Convection, A.A. Dehbi, M.W. Golay, and M.S. Kazimi (September 1995). 038 A Methodology for Modular Nuclear Power Plant Design and Construction, C. Lapp and M.W. Golay (October 1995). 039 A Mental Procedure for More Reliable Specification of System Control Software Requirements, C.W. Kang, M. Ouyang, and M.W. Golay (December 1995). 040 Complete Safety Software Testing: A Formal Method, J.R. Lunglhofer, M.W. Golay, and D.D. Lanning (January 1996). 041 Quantitative Methodology for Surveillance Interval Extension at Nuclear Power Plants, H. Masui and M.W. Golay (June 1996). 042 An Investigation of How Powerful a Nuclear Reactor Can Be, T.L. Stoops and M.W. Golay (June 1996). 043 A Study for Improving Reliability and Capacity Factor of the PWR Feedwater Supply System, F. Li and M.W. Golay (June 1996). 044 A Strategy for Reducing Forced Outage Rates in Commercial Nuclear Reactors with a Main Feed Pump Case Study, T.J. Moore and N.E. Todreas (July 1996). 045 Modeling and Design of a Reload PWR Core for a 48-Month Fuel Cycle, M.V. McMahon, M.J. Driscoll, and N.E. Todreas (July 1996). 046 Improvement in Nuclear Plant Capacity Factors Through Longer Cycle Length Operation, Annual Report, N.E. Todreas and M.V. McMahon (July 1996). 047 Dependency of Human Operator Performance Quality Upon Task Complexity, J. Automo and M.W. Golay (September 1996). 048 Passive Containment Cooling System for Large PWRs Using Thermosyphon Loops, M. Leiendecker, N.E. Todreas, M.J. Driscoll and A. Hurtado (October 1996). 049 Economic Analysis of Implementing a Four-Year Extended Operating Cycle in Existing PWRs, C.S. Handwerk, M.J. Driscoll, N.E. Todreas and M.V. McMahon (January 1997). iv

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