UN approximation to critical slab problem for one-speed neutrons with isotropic, forward and backward scattering
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H. Öztürk
Abstract
A modified version of the UN method is used to solve the critical slab problem in the case of a combination of forward and backward scattering with isotropic scattering in a uniform finite slab. The Marshak boundary condition is used for the calculation of the critical slab thicknesses and it is shown that the method gives accurate results in one-dimensional geometry and converges rapidly with easily executable equations. The presented numerical results are compared with the results available in literature.
Kurzfassung
UN Approximation zur Lösung des Ein-Gruppen-Transportproblems in kritischen Platten mit isotroper Streuung und Vorwärts- und Rückwärtsstreuung. Eine modifizierte Version der UN Methode wurde verwendet zur Lösung des Ein-Gruppen-Transportproblems in kritischen Platten für den Fall einer Kombination von Vorwärts- und Rückwärtsstreuung mit isotroper Streuung in einer gleichförmigen endlichen Platte. Die Marshak Randbedingungen wurden verwendet für die Berechnung der Dicken der kritischen Platten. Die Methode liefert genaue Ergebnisse für eindimensionale Geometrie und konvergiert schnell mit leicht ausführbaren Gleichungen. Die vorgestellten numerischen Ergebnisse wurden verglichen mit Ergebnissen aus der Literatur.
References
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© 2010, Carl Hanser Verlag, München
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Integrated online condition monitoring system for nuclear power plants
- Performance analysis of 233U for fixed bed nuclear reactors
- 3D thermal hydraulic simulation of the hot channel of a typical material testing reactor under normal operation conditions
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- Nuclear model calculation on charged particle induced reactions to produce 85Sr for diagnostic and endotherapy
- Neutronic and burn-up calculations of heterogeneous Thorium/Uranium fuel in pressurized water reactors
- Research on pitting corrosion of steam generator heat transfer tubes based on acoustic emission
- Application of the Chebyshev polynomial (TN and UN) approximation to reflected slab geometry in the neutron transport equation and computation of critical half thicknesses
- UN approximation to critical slab problem for one-speed neutrons with isotropic, forward and backward scattering
- The albedo problem for pure-quadratic anisotropic scattering with İnönü scattering
- Technical Notes/Technische Mitteilungen
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Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Integrated online condition monitoring system for nuclear power plants
- Performance analysis of 233U for fixed bed nuclear reactors
- 3D thermal hydraulic simulation of the hot channel of a typical material testing reactor under normal operation conditions
- Analysis of the processes in the target cooling system of the W7-X fusion experiment
- Nuclear model calculation on charged particle induced reactions to produce 85Sr for diagnostic and endotherapy
- Neutronic and burn-up calculations of heterogeneous Thorium/Uranium fuel in pressurized water reactors
- Research on pitting corrosion of steam generator heat transfer tubes based on acoustic emission
- Application of the Chebyshev polynomial (TN and UN) approximation to reflected slab geometry in the neutron transport equation and computation of critical half thicknesses
- UN approximation to critical slab problem for one-speed neutrons with isotropic, forward and backward scattering
- The albedo problem for pure-quadratic anisotropic scattering with İnönü scattering
- Technical Notes/Technische Mitteilungen
- Targetry of Y2O3 on a copper substrate for the non-carrier-added 89Zr production via 89Y(p, n)89Zr reaction
