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      U 1 and P 1 approximations to neutron transport equation for diffusion length calculation Translated title: U 1 and P 1 Approximationen zur Lösung der Neutronentransportgleichung für die Berechnung der Diffusionslänge

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      1 , 2
      Kerntechnik
      Carl Hanser Verlag

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          Abstract

          U 1 and P 1 approximations are used for the calculation of asymptotic relaxation length in one-dimensional neutron transport equation. The approximation methods are applied to anisotropic neutron transport equation with backward and forward scattering. The methods are based on the series expansion of the neutron angular flux in terms of the Chebyshev polynomials of second kind and Legendre polynomials. By applying the first order approximation to the transport equation, asymptotic relaxation lengths are calculated. Numerical results obtained from both methods are compared with each other.

          Kurzfassung

          U 1 und P 1 Approximationen wurden verwendet für die Berechnung der asymptotischen Relaxationslünge in der eindimensionalen Neutronentransportgleichung. Die Näherungsmethoden wurden angewendet auf die anisotrope Neutronentransportgleichung mit Rückwürts- und Vorwürtsstreuung. Die Methoden basieren auf der Reihenexpansion der Winkelverteilung des Neutronenflusses in Form von Tschebyscheff-Polynomen zweiter Art und Legendre-Polynomen. Durch Anwendung der Nüherung erster Art auf die Transportgleichung werden asymptotische Relaxationslüngen berechnet. Die mit beiden Methoden erhaltenen numerischen Ergebnisse werden miteinander verglichen.

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          Most cited references4

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          Application of the U N method to the reflected critical slab problem for one-speed neutrons with forward and backward scattering

          The U N method is used to solve the critical slab problem for reflecting boundary conditions in one-speed neutron transport theory. The isotropic scattering kernel with the combination of forward and backward scattering is chosen for the neutrons in a uniform finite slab. It is shown that the method converges rapidly with easily executable equations. The presented numerical results are compared with the results available in the literature.
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            T N approximation to neutron transport equation and application to critical slab problem. J. Quant. Spectrosc

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              TN method for the critical thickness of one-speed neutrons in a slab with forward and backward scattering

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                Author and article information

                Journal
                kt
                Kerntechnik
                Carl Hanser Verlag
                0932-3902
                2195-8580
                28 June 2013
                : 78
                : 3
                : 238-240
                Affiliations
                1 Ahmet Bülbül, E-mail: ahmetbulbul@ 123456gmail.com
                2 Hakan üztürk, Osmaniye Korkut Ata University, Faculty of Arts and Sciences, Department of Physics, 80000 Osmaniye, Turkey
                Article
                KT110278
                10.3139/124.110278
                e94f4a2d-4602-46d5-b7f6-19a58d1f22ff
                © 2013, Carl Hanser Verlag, München
                History
                : 20 June 2012
                Page count
                References: 16, Pages: 3
                Categories
                Technical Contributions/Fachbeiträge

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

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