Approximation method for the adjoint neutron spectrum in heterogeneous media
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L. C. Suster
Abstract
A method is proposed for the numerical and analytical calculations of the adjoint neutron spectrum in the resonance energy region, for narrow resonances, in order to reduce the numerical computations involved. The adjoint neutron spectrum of infinite cylindrical fuel cell is calculated according to a very simple analytical method with reasonable level of accuracy. The results obtained with this analytical method were compared to a reference solution obtained with a numerical solution of the neutron balance adjoint equations. The adjoint neutron spectrum is useful to determine the neutron resonance absorption, so that multigroup adjoint cross sections used by the adjoint diffusion equation can be obtained.
Kurzfassung
Es wird ein Verfahren vorgeschlagen für die numerische und analytische Berechnung des adjungierten Neutronenspektrums in der Resonanzenergieregion, für schmale Resonanzen, um so den damit verbundenen numerischen Rechenaufwand zu reduzieren Das adjungierte Neutronenspektrum einer infiniten zylindrischen Brennelementzelle wird mit Hilfe einer sehr einfachen analytischen Methode und einem vernünftigen Genauigkeitsgrad berechnet. Die mit dieser analytischen Methode erhaltenen Ergebnisse wurden verglichen mit einer Referenzergebnis, das mit Hilfe einer numerischen Lösung der adjungierten Neutronenbilanzgleichung erhalten wurde. Das adjungierte Neutronenspektrum ist hilfreich zur Bestimmung der Neutronenresonanzabsorption so dass adjungierte Multigruppenquerschnitte erhalten werden, die in der adjungierten Diffusionsgleichung verwendet werden können.
References
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© 2005, Carl Hanser Verlag, München
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- Contents
- Summaries/Kurzfassungen
- Summaries/Kurzfassungen
- Technical Contributions/Fachbeiträge
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- Validation of the CFD code FLUENT by post test calculation of a ROCOM experiment with density driven coolant mixing
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- Fire hazard analysis at Ignalina Nuclear Power Plant
- Analysis of future nuclear power plants competitive investment costs with stochastic methods
- Approximation method for the adjoint neutron spectrum in heterogeneous media
- Positive temperature reactivity coefficient of a TRIGA reactor at room temperature
- The singular eigenfunction method: the critical slab problem for linearly anisotropic scattering
- Effects of spectral shifting in an inertial confinement fusion system
- Technical Notes/Technische Mitteilungen
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Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries/Kurzfassungen
- Technical Contributions/Fachbeiträge
- Simulation of the neutronic-thermal hydraulic stability behaviour of boiling water reactors
- Validation of the CFD code FLUENT by post test calculation of a ROCOM experiment with density driven coolant mixing
- Production of 4He and 3He from tantalum and tungsten irradiated with nucleons at energies up to 1 GeV
- Fire hazard analysis at Ignalina Nuclear Power Plant
- Analysis of future nuclear power plants competitive investment costs with stochastic methods
- Approximation method for the adjoint neutron spectrum in heterogeneous media
- Positive temperature reactivity coefficient of a TRIGA reactor at room temperature
- The singular eigenfunction method: the critical slab problem for linearly anisotropic scattering
- Effects of spectral shifting in an inertial confinement fusion system
- Technical Notes/Technische Mitteilungen
- A fool proof non-proliferation nuclear reactor concept
