Normalized distribution of the continuous (a) and the 28-group spectrum (b) of neutrons: 1 – spontaneous fission; 2 – (α,n)-reactions; 3 – total vector.

 
 
  Part of: Shamanin IV, Bedenko SV, Nesterov VN, Lutsik IO, Prets AA (2018) Solution of neutron-transport multigroup equations system in subcritical systems. Nuclear Energy and Technology 4(1): 79-85. https://doi.org/10.3897/nucet.4.29837