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  1. openmc-dev/openmcopenmc-dev/openmcPublic

    OpenMC Monte Carlo Code

    Python 1.1k 676

  2. mit-crpg/OpenMOCmit-crpg/OpenMOCPublic

    A method of characteristics code for nuclear reactor physics calculations.

    C++ 190 90

  3. mit-crpg/PINSPECmit-crpg/PINSPECPublic

    A Monte Carlo code for simple spectral calculations in nuclear reactor applications.

    C++ 10 4

  4. ANE-Single-Step-MGXSANE-Single-Step-MGXSPublic archive

    LaTeX source for "A Single-Step Framework to Generate Spatially Self-Shielded Multi-Group Cross Sections from Monte Carlo Transport Simulations" published in the Annals of Nuclear Energy (2019).

    TeX