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.


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