Center for Advanced Nuclear Energy Systems (CANES): Recent submissions

Now showing items 34-36 of 109

    • MCODE, Version 2.2: An MCNP-ORIGEN DEpletion Program 

      Xu, Z.; Hejzlar, Pavel (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2008-12)
      MCODE Version 2.2 is a linkage program, which combines the continuous-energy Monte Carlo code, MCNP-4C, and the one-group depletion code, ORIGEN2, to perform burnup calculations for nuclear fission reactor systems. MCNP ...

    • A System Dynamics Study of the Nuclear Fuel Cycle with Recycling: Options and Outcomes for the US and Brazil 

      Busquim e Silva, R.; Kazimi, Mujid S.; Hejzlar, Pavel (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2008-11)
      A system dynamics simulation technique is applied to generate a new version of the CAFCA code to study mass flows in the nuclear fuel cycle, and the impact of different options for advanced reactors and fuel recycling ...

    • 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 ...