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Steady-state fast neutron spectra in slabs on natural uranium-a comparison of diffusion and transport theories

Space-dependent fast neutron spectra have been calculated in slabs of natural uranium by solving the multigroup diffusion equation. It is shown that the eigenfunction expansion method can be used even in this case when the fission term is present, by using the biorthogonality property between the eigenfunctions of the actual matrix and those of the transpose matrix. These results have been compared with the corresponding results based on transport theory. Except close to the source and the free boundary, the authors find good agreement between the two sets of results.