S4 Solution of the Transport Equation for Eigenvalues: Isotropic, Forward and Backward Scattering in a Slab

İleri ve geri saçılmalı sonlu homojen bir dilimde tek enerjili nötronların özdeğer spektrumu için nötron transport denklemi nümerik olarak çözülmüştür. Transport denklemindeki nötron saçılmasını temsilen, ileri-geri-izotropic (FBI) saçılma fonksiyonu tercih edilmiştir. Daha sonra, çift-mertebeli Gauss-Legendre kuadratür seti ile integral dönüşüm tekniği kullanılarak transport denklemi diskret-ordinatlar haline dönüştürülmüştür. Son olarak, faklı saçılma, ileri ve geri saçılma parametreleri kullanılarak zayıf yutulmalı bir ortamdan kuvvetli saçılmalı bir ortama kadar özdeğerler hesaplanmıştır. Bütün hesaplamalarda GaussLegendre kuadratür setleri kullanılmış ve hesaplanan özdeğerler çizelgelerde verilmiştir

Transport Denkleminin Özdeğerler için S4Çözümü: Dilimde İzotropik, İleri ve Geri Saçılma

The neutron transport equation is solved numerically for monoenergetic neutrons in a finite homogeneous slab with backward and forward scattering for the eigenvalue spectrum. The forward-backward-isotropic (FBI) scattering kernel is chosen for representing the neutron scattering in transport equation. Then, the transport equation is converted into a discrete ordinates form by using the integral transform technique with the even-order Gauss-Legendre quadrature set. Finally, the eigenvalues are calculated for a medium from weakly absorbing to highly scattering condition using various values of the scattering, backward and forward scattering parameters. Gauss-Legendre quadrature sets are used for all calculations and the calculated eigenvalues are given in the tables

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