Modified UN method for the reflected critical slab problem with forward and backward scattering
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H. Öztürk
Abstract
The critical slab problem is investigated in one-speed neutron transport theory for reflecting boundary conditions using second kind Chebyshev polynomials approximation. The forward-backward-isotropic scattering kernel is used in a uniform homogeneous slab. The critical slab thicknesses for various values of the collision parameter, forward and backward scattering and reflection coefficient are given in the tables together with the ones available in literature and they are in good agreement.
Kurzfassung
Das Problem kritischer Platten wurde untersucht in der Eingruppen-Neutronentransporttheorie für reflektierende Randbedingungen mit Hilfe der Tschebyscheff-Polynome zweiter Art. Der vorwärts-rückwärts-isotrope Streukern wird in einem gleichförmig homogenen Stab verwendet. Die kritischen Stabdicken wurden für verschiedene Werte der Kollisionsparameter, der Vorwärts- und Rückwärtsstreuung und des Reflektionskoeffizienten berechnet und werden tabellarisch dargestellt zusammen mit den Literaturwerten, mit denen sie eine gute Übereinstimmung zeigen.
References
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© 2011, Carl Hanser Verlag, München
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Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Comparison between CAREB code calculations and LOCA test results in the FUMEX III project
- Calculation of moderator circulation in IPHWR using a porosity approach
- Simulation of natural circulation in a rectangular loop using CFD code PHOENICS
- CFD analysis of passive autocatalytic recombiner interaction with atmosphere
- Review and investigations of oscillatory flow behaviour of a horizontal ceiling opening for nuclear containment and fire safety analysis
- CFD simulation of thermal discharge behaviour in the Kadra reservoir at the Kaiga atomic power station
- Inverse problems using Artificial Neural Networks in long range atmospheric dispersion
- Sipping tests for the irradiated fuel elements of the TR-2 research reactor
- Neutron multiplication in source driven subcritical nuclear systems
- Cyclotron production of 101Pd/101mRh radionuclide generator for radioimmunotherapy
- Investigation of cross sections of reactions used in neutron activation analysis
- Modified UN method for the reflected critical slab problem with forward and backward scattering
