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

Now showing items 22-24 of 45

    • A Benchmark Study of Computer Codes for System Analysis of the Nuclear Fuel Cycle 

      Guérin, Laurent; Feng, Bo; Hejzlar, Pavel; Forget, Benoit; Kazimi, Mujid S.; e.a. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2009-04)
      As use of nuclear energy is expected to expand in different parts of the world, several codes that describe the nuclear fuel cycle system are currently under development, featuring a range of capabilities and different ...

    • 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 ...