Explicit formulation of a nodal transport method for discrete ordinates calculations in two-dimensional fixed-source problems
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A. Tres
Abstract
In this work a study of two-dimensional fixed-source neutron transport problems, in Cartesian geometry, is reported. The approach reduces the complexity of the multidimensional problem using a combination of nodal schemes and the Analytical Discrete Ordinates Method (ADO). The unknown leakage terms on the boundaries that appear from the use of the derivation of the nodal scheme are incorporated to the problem source term, such as to couple the one-dimensional integrated solutions, made explicit in terms of the x and y spatial variables. The formulation leads to a considerable reduction of the order of the associated eigenvalue problems when combined with the usual symmetric quadratures, thereby providing solutions that have a higher degree of computational efficiency. Reflective-type boundary conditions are introduced to represent the domain on a simpler form than that previously considered in connection with the ADO method. Numerical results obtained with the technique are provided and compared to those present in the literature.
Kurzfassung
In dieser Arbeit wird über Untersuchungen bei Transportproblemen mit zweidimensionalen Fixed-Source-Quelldaten in kartesischer Geometrie berichtet. Der Ansatz reduziert die Komplexität des vielschichtigen Problems durch Anwendung einer Kombination von nodalen Schemata und Analytischer Diskrete Ordinaten Methode (ADO). Die unbekannten Leckage-Terme am Rand, die durch die Verwendung der Ableitung des nodalen Systems zustande kommen, werden in den Quellterm einbezogen, um so eindimensionale integrierte Lösungen zu koppeln, ausgedrückt in Form von x und y räumlichen Variablen. Die Formulierung führt zu einer erheblichen Reduzierung der Ordnung der damit verbundenen Eigenwertprobleme, wenn sie mit den üblichen symmetrischen Quadraturen kombiniert werden, und liefern damit Lösungen mit höherer Recheneffizienz. Reflexionsrandbedingungen werden eingeführt, um den Bereich in einfacherer Form darzustellen als die vorher im Zusammenhang mit der ADO-Methode verwendeten Verfahren. Die mit dieser Technik erhaltenen numerischen Ergebnisse werden vorgestellt und mit denen in der Literatur verglichen.
References
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© 2014, Carl Hanser Verlag, München
Artikel in diesem Heft
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- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- A model-based approach to operational event groups ranking
- Application of the method for uncertainty and sensitivity evaluation to results of PWR LBLOCA analysis calculated with the code ATHLET. Part 2: sensitivity analysis
- Statistical Large-Break LOCA analysis for PWRs with combined ECC injection
- Analysis of the CSF model for simulated loss of coolant accident conditions
- Performance of two fluid model based numeric tool with pressure and enthalpy as independent variables for simulation of two phase flow in axial and radial direction
- Pre-decommissioning complex engineering and radiation inspection of the WWR-M reactor
- Analysis of the source term formation in a severe accident initiated by end fitting failure in CANDU type reactors
- Neutron flux investigation on certain alternative fluids in a hybrid system by using MCNPX Monte Carlo transport code
- Analytical investigation of lignite and its ash samples taken from the Afşin-Elbistan coal basin in Turkey
- Explicit formulation of a nodal transport method for discrete ordinates calculations in two-dimensional fixed-source problems
- T1 and U1 approximations to neutron transport equation in one-dimensional spherical geometry
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- A model-based approach to operational event groups ranking
- Application of the method for uncertainty and sensitivity evaluation to results of PWR LBLOCA analysis calculated with the code ATHLET. Part 2: sensitivity analysis
- Statistical Large-Break LOCA analysis for PWRs with combined ECC injection
- Analysis of the CSF model for simulated loss of coolant accident conditions
- Performance of two fluid model based numeric tool with pressure and enthalpy as independent variables for simulation of two phase flow in axial and radial direction
- Pre-decommissioning complex engineering and radiation inspection of the WWR-M reactor
- Analysis of the source term formation in a severe accident initiated by end fitting failure in CANDU type reactors
- Neutron flux investigation on certain alternative fluids in a hybrid system by using MCNPX Monte Carlo transport code
- Analytical investigation of lignite and its ash samples taken from the Afşin-Elbistan coal basin in Turkey
- Explicit formulation of a nodal transport method for discrete ordinates calculations in two-dimensional fixed-source problems
- T1 and U1 approximations to neutron transport equation in one-dimensional spherical geometry
