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  1. openmc-dev/openmc Public

    OpenMC Monte Carlo Code

    Python 822 537

  2. mit-crpg/OpenMOC Public

    A method of characteristics code for nuclear reactor physics calculations.

    C++ 158 84

  3. mit-crpg/PINSPEC Public

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

    C++ 10 3

  4. ANE-Single-Step-MGXS Public 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

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April 2025

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