Application of the UN approximation to the neutron transport equation in slab geometry
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A. Bülbül
Abstract
The critical slab problem of the one-speed and one dimensional neutron transport equation for an isotropic homogeneous medium was studied by using the Chebyshev polynomial approximation, i. e. UN method. The results obtained by the UN method for various c values, using the two type boundary conditions which are known as Mark and Marshak boundary conditions, are presented in tables. The tables also include the results obtained by the PN method for comparison.
Kurzfassung
Das Kritikalitätsproblem in der Eingruppen-Neutronentransportgleichung für isotrope homogene Medien wurde untersucht mit Hilfe der Chebyshev Approximation, d. h. der UN-Methode. Die mit der UN-Methode unter Verwendung der Mark and Marshak Randbedingungen erhaltenen Ergebnisse für verschiedene c-Werte werden in tabellarischer Form vorgestellt. Zum Vergleich beinhalten die Tabellen auch die Ergebnisse, die man mit der PN-Methode erhält.
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© 2008, Carl Hanser Verlag, München
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
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
