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Nötron Transportu için Küresel Geometride Özdeğer Hesaplaması

Eigenvalue Calculation for Transport Theory in Spherical Geometry

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Abstract (2. Language): 
In this study, eigenvalue and eigenvector of transport equation which are current topics of nuclear physics are investigated. Spherical geometry problem of neutron was reduced the slab geometry problem with our approach. This equation is then solved in this slab geometry with producing eigenvalue
Abstract (Original Language): 
Bu çalışmada nükleer fiziğin güncel konularından biri olan transport eşitliğinin özdeğeri incelendi. Analizi zor olan nötronların küresel geometri problemi bizim yaklaşımımızla düzlem geometri problemine indirgenmiştir. Sonrada bu geometride özdeğerler üretilerek çözüme ulaşılmıştır.
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