Browsing Nuclear Fuel Cycle Technology and Policy Program (NFC) - Technical Reports by Title

Now showing items 42-45 of 45

    • Thermal Hydraulic Analysis of a Low Enrichment Uranium Core for the MIT Research Reactor 

      Ko, Yu-Chih; Hu, Lin-Wen; Kazimi, Mujid S. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2008-01)
      The MIT research reactor (MITR) is converting from the existing high enrichment uranium (HEU) core to a low enrichment uranium (LEU) core using a high-density monolithic UMo fuel. The design of an optimum LEU core for ...

    • Thermal Hydraulic and Economic Analysis of Grid-Supported Hydride and Oxide Fueled PWRs 

      Shuffler, C.; Trant, J.; Todreas, Neil E.; Romano, A. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2006-09)
      This report advances the Hydride Fuels Project, a collaborative effort between UC Berkeley and MIT aimed at investigating the potential benefits of hydride fuel use in light water reactors (LWRs). This effort involves ...

    • UPDATE ON THE COST OF NUCLEAR POWER 

      Du, Yangbo; Parsons, John E. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2009-05)
      We update the cost of nuclear power as calculated in the MIT (2003) Future of Nuclear Power study. Our main focus is on the changing cost of construction of new plants. The MIT (2003) study provided useful data on the ...

    • Wire Wrapped Hexagonal Pin Arrays for Hydride Fueled PWRs 

      Diller, Peter; Todreas, Neil E. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2006-01)
      This work contributes to the Hydride Fuels Project, a collaborative effort between UC Berkeley and MIT aimed at investigating the potential benefits of hydride fuel use in light water reactors (LWRs). Core design is ...