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      The critical slab problem for pure-triplet anisotropic scattering by singular eigenfunction method

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      1 , * , , 2 , * ,
      Kerntechnik
      Carl Hanser Verlag

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          Abstract

          The infinite medium Green function can be written by using the jump condition, found Case's eigenfunctions. Thus, any reactor theory problem which is inplane geometry such the criticality problem as can be investigated by using the proper boundary conditions and suggested flux definitions. By using the criticality equation the critical thicknesses can be calculated as numerically. The selected numerical results can be tabulated.

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          Most cited references7

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          Neutron Transport with Anisotropic Scattering

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            The CN Method of Solving the Transport Equation: Application to Plane Geometry

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              Solution of the CN equations using singular eigenfunctions and applications

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                Author and article information

                Journal
                kt
                Kerntechnik
                Carl Hanser Verlag
                0932-3902
                2195-8580
                18 December 2017
                : 82
                : 6
                : 693-699
                Affiliations
                1 Kırıkkale University, Kırıkkale Vocational School, Center Campus, Kırıkkale 71450, Turkey
                2 Ministery of Education, General Directorate of Secondary Education, Çankaya, Ankara, Turkey
                Author notes
                [* ] Corresponding author: E-mail: tureci@ 123456gmail.com
                Article
                KT110806
                10.3139/124.110806
                56b8c18d-3149-4997-8efc-497b77f60e9f
                © 2017, Carl Hanser Verlag, München
                History
                : 23 March 2017
                Page count
                References: 9, Pages: 7
                Categories
                Technical Note

                Materials technology,Materials for energy,Nuclear physics
                Materials technology, Materials for energy, Nuclear physics

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