The reflected critical slab problem for one-speed neutrons with strongly anisotropic scattering
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H. Öztürk
Abstract
The Chebyshev polynomial approximation is used to solve the reflected critical slab problem for one-speed neutrons in a slab with strongly anisotropic scattering. The scattering kernel which is a combination of backward-forward-isotropic scattering and linearly anisotropic scattering is chosen in a uniform finite slab. The critical slab thicknesses are given for different degrees of reflection, backward-forward and linear anisotropy. Calculated numerical results for the critical thickness are in good agreement with the results available in literature.
Kurzfassung
Die Tschebyscheff Polynome werden angewendet zur Lösung des Eingruppen-Transportproblems in kritischen Platten mit Reflektor für Neutronen mit stark anisotroper Streuung. Zur Beschreibung der Neutronenstreuung in einer endlichen homogenen Platte wurde ein Streukern gewählt, der eine Kombination von rückwärts-vorwärts-isotroper Streuung ist. Die Dicken der kritischen Platten werden angegeben für verschiedene Werte der Reflexion, der rückwärts-vorwärts und der linear anisotropen Streuung. Die numerischen Ergebnisse für die kritischen Dicken stimmen gut mit den in der Literatur angegebenen Werten überein.
References
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© 2008, Carl Hanser Verlag, München
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Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Analysis of the hydrogen behaviour in compartments of the Ignalina nuclear power plant
- Determination of the RBMK-1500 reactor passport characteristics
- Technical feasibility of using RU-43 fuel in the CANDU-6 reactors of the Cernavoda NPP
- Computational study of moderator flow and temperature fields in the calandria vessel of a heavy water reactor using the PHOENICS code
- Regulatory requirements on level 2 PSA in Germany and their associated potential to improve emergency management
- Dynamic structure response due to reactor cooling piping system failure
- Uncertainty in activation cross-section calculations at intermediate proton energies
- The LTSN solution of the transport equation for one-dimensional cartesian geometry with c = 1
- Application of the UN approximation to the neutron transport equation in slab geometry
- The reflected critical slab problem for one-speed neutrons with strongly anisotropic scattering
- The analytical representation of the fundamental mode in 1-D-geometry for the CANDLE burn-up phenomenon
