Resonance cross sections, Doppler effect, Resonance integrals, Neutron scattering, differential scattering cross section, neutron kinematics, Center of Mass and Lab systems, transfer probability, transfer cross section, transport cross section, neutron leathargy, moderating power and moderating ratio.Neutron flux, current partial currents. The neutron transport equation: derivation, boundary conditions, approximations, steady state, energy and velocity variables, one speed, multi-group, one dimensional, derivation of the diffusion equation from the transport equation.Neutron slowing down theory: infinite homogenous medium approximation to the transport equation, neutron spectra in the fission region (above 0.1 MeV), slowing down in a hydrogenous medium with and without absorption, slowing down in a non-hydrogenous medium with and without absorption, resonance absorption, slowing down in a thermal region, Maxwellian distribution, non-Maxwellian distribution. Fuel lattice cell calculations: effect of fuel lumping on the neutron multiplication, cell homogenization, core homogenization, cross section collapsing from the ENDFB library, spectrum codes, collapsing to few group cross sections,LEOPARD code: scope of the overall calculation task, preparation of the input file, interpretation of the output file, sample problems excluding burn-up.
