MC2-3 is a multigroup cross section generation code for nuclear reactor design and analysis. Various geometries – homogeneous medium, 1D unit cell, 2D or 3D hexagonal or Cartesian assembly – can be solved with the collision probability method (CPM) or the method of characteristics (MOC) using ultrafine or hyperfine energy groups. The resolved resonances are self-shielded using pointwise cross sections reconstructed with analytic Doppler broadening at specified isotopic temperatures. The unresolved resonances are self-shielded using the analytic resonance integral method. For accurately producing broad group cross sections, the code can be coupled with external two-dimensional ultrafine group transport calculation codes such as TWODANT and PARTISN. The code produces broad group neutron and gamma cross sections as well as gamma production matrices and KERMA factors.
More information can be found at https://www.anl.gov/technology/project/mc2-3-multigroup-cross-sections-fast-reactors