Un Approximation To Neutron Transport Equation In Slab Geometry; Computation Of General Eigenvalue Spectrum

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dc.authoridTR1934en_US
dc.contributor.authorBulbul, Ahmet
dc.contributor.authorAnli, Fikret
dc.date.accessioned2015-04-03T08:06:18Z
dc.date.available2015-04-03T08:06:18Z
dc.date.issued2007
dc.departmentÄ°stanbul Beykent Ãœniversitesien_US
dc.description.abstractGeneral 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.en_US
dc.identifier.citationJournal of Science and Technology 1 (2), 2007, 293-301tr_TR
dc.identifier.issn1307-3818
dc.language.isoenen_US
dc.relation.publicationcategoryMakale - Ulusal Hakemli Dergi - Kurum Öğretim Elemanıen_US
dc.subjectChebyshev Polynomialstr_TR
dc.subjectneutron transport in slab geometrytr_TR
dc.subjecteigenvalue spectrumtr_TR
dc.titleUn Approximation To Neutron Transport Equation In Slab Geometry; Computation Of General Eigenvalue Spectrumen_US
dc.typeArticleen_US

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