Application of the Laplace transform method for the albedo boundary conditions in multigroup neutron diffusion eigenvalue problems in slab geometry
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C. Z. Petersen
Abstract
In this paper the application of the Laplace transform method is described in order to determine the energy-dependent albedo matrix that is used in the boundary conditions multigroup neutron diffusion eigenvalue problems in slab geometry for nuclear reactor global calculations. In slab geometry, the diffusion albedo substitutes without approximation the baffle-reflector system around the active domain. Numerical results to typical test problems are shown to illustrate the accuracy and the efficiency of the Chebysheff acceleration scheme.
Kurzfassung
In der vorliegenden Arbeit wird die Laplace-Transformationsmethode zur Bestimmung der Energie-abhängigen Albedo-Matrix beschrieben, die für Albedo-Randbedingungen in Multigruppen-Berechnungen von Neutronen-Diffusions-Eigenwertproblemen in Slab-Geometrie verwendet wird. In Slab-Geometrie ersetzt die Diffusions-Albedo ohne Approximation das Baffle-Reflektorsystem um den aktiven Bereich herum. Numerische Ergebnisse typischer Fragestellungen werden gezeigt, um die Genauigkeit und die Effizienz des Tschebyscheff-Beschleunigungsschemas zu zeigen.
References
1 Alcouffe, R. E.; O'Dell, R. D.: Transport Calculations for Nuclear Reactors, CRC Handbook of Nuclear Reactor Calculations, vol. 1, CRC Press, Inc., Florida, 1986Search in Google Scholar
2 Pannekoek, A.: A History of Astronomy. Dover Publications, New York, 1961Search in Google Scholar
3 Fladmark, G. E.: Numerical Reactor Calculations. IAEA – SM – 154/20, pp. 497–507, Vienna, 1972Search in Google Scholar
4 Petersen, C. Z.: Aplicação da Transformada de Laplace para Determinação de Condições de Contorno tipo Albedo para Cálculos Neutrônicos. M. Sc. dissertation, PROMEC/UFRGS, (in Portuguese), Brazil, 2008Search in Google Scholar
© 2009, Carl Hanser Verlag, München
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- Modified Chebyshev polynomial (UN) approximation in the neutron transport theory and computation of critical half thicknesses
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Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- AVR prototype pebble bed reactor: a safety re-evaluation of its operation and consequences for future reactors
- Design Concept of the High Performance Light Water Reactor
- Behavior of CANDU fuel under power pulse conditions at the TRIGA reactor of INR Pitesti
- Plate heat exchanger – inertia flywheel performance in loss of flow transient
- Performance analyses of the communication networks of a modern supervision and control system of research reactors
- Thermal analytical model for MoO3 ampoules irradiated in a high neutron flux
- Effect of using various grades of plutonium in the protective liquid wall of an IFE type fusion reactor
- A discrete ordinates scheme for void fraction evaluation with nonstandard reflective conditions and weakly divergent beams
- Application of the Laplace transform method for the albedo boundary conditions in multigroup neutron diffusion eigenvalue problems in slab geometry
- Modified Chebyshev polynomial (UN) approximation in the neutron transport theory and computation of critical half thicknesses
- Optimizing the dynamic response of the H. B. Robinson nuclear plant using multiobjective particle swarm optimization
- Assessment for inside building dispersion of aerosol from an outdoor radiological release
- Technical Notes/Technische Mitteilungen
- Analysis of a steam generator tube rupture under realistic initial and boundary conditions
