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A Super Critical Carbon Dioxide Cycle for Next Generation Nuclear Reactors
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 2004-03)
A systematic, detailed major component and system design evaluation and multiple-parameter optimization under practical constraints has been performed of the family of supercritical CO[subscript 2] Brayton power cycles for ...
Design of Compact Intermediate Heat Exchangers for Gas Cooled Fast Reactors
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 2004-05)
Two aspects of an intermediate heat exchanger (IHX) for GFR service have been
investigated: (1) the intrinsic characteristics of the proposed compact printed circuit heat
exchanger (PCHE); and (2) a specific design ...
Thermal-Hydraulic Analysis of Innovative Fuel Configurations for the Sodium Fast Reactor
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 2009-08)
The sodium fast reactor (SFR) is currently being reconsidered as an instrument for
actinide management throughout the world, thanks in part to international programs such
as the Generation-IV and especially the Global ...