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Öğe Un Approximation To Neutron Transport Equation In Slab Geometry; Computation Of General Eigenvalue Spectrum(2007) Bulbul, Ahmet; Anli, FikretGeneral theoretical scheme for the UN method and evolution of general eigenvalue spectrum are described. Firstly, applicability of UN method to one dimensional slab geometry neutron transport problem is discussed and then eigenvalue spectrum is calculated for isotropic scattering with different values of parameter c (where c is the mean number of secondary neutrons per collision and known as the fundamental eigenvalue). Results of the UN method showed that both discrete and continuum eigenvalues are present as in the case of PN method. All the results computed by both methods i.e. UN and PN methods are presented side by side in the Tables for the comparisons.
