Nuclear Fuel Cycle Technology and Policy Program (NFC) - Technical Reports: Recent submissions

Now showing items 25-27 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 ...

    • PWR Transition to a Higher Power Core Using Annular Fuel 

      Beccherle, J.; Hejzlar, Pavel; Kazimi, Mujid S. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2007-09)
      The internally and externally cooled annular fuel is a new type of fuel for PWRs that enables an increase in core power density by 50% within the same or better safety margins as traditional solid fuel. Each annular fuel ...

    • Sensitivity of Economic Performance of the Nuclear Fuel Cycle to Simulation Modeling Assumptions 

      Bonnet, Nicephore; Kazimi, Mujid S. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2007-07)
      Comparing different nuclear fuel cycles and assessing their implications requires a fuel cycle simulation model as complete and realistic as possible. In this report, methodological implications of modeling choices are ...