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1. openmc-dev/openmc openmc-dev/openmc Public

   OpenMC Monte Carlo Code

   Python 933 596

2. mit-crpg/OpenMOC mit-crpg/OpenMOC Public

   A method of characteristics code for nuclear reactor physics calculations.

   C++ 175 85

3. mit-crpg/PINSPEC mit-crpg/PINSPEC Public

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

   C++ 10 3

4. ANE-Single-Step-MGXS 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