Deterministic calculation of grey Dancoff factors in cluster cells with cylindrical outer boundaries
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L. Jenisch Rodrigues
Abstract
In the present work, the WIMSD code routine PIJM is modified to compute deterministic Dancoff factors by the collision probability definition in general arrangements of partially absorbing fuel rods. Collision probabilities are calculated by an efficient integration scheme of the third-order Bickley functions, which considers each cell region separately. The effectiveness of the method is assessed by comparing grey Dancoff factors as calculated by PIJM, with those available in the literature by the Monte Carlo method, for the irregular geometry of the Canadian CANDU and CANFLEX assemblies. Dancoff factors at several different fuel pin positions are found in very good agreement with the literature results.
Kurzfassung
In dem vorliegenden Beitrag wird die WIMSD Code Routine PIJM modifiziert zur Berechnung deterministischer Dancoff-Faktoren durch Bestimmung der Stoßwahrscheinlichkeiten bei üblicher Anordnung von teilabsorbierenden Brennstäben. Die Stoßwahrscheinlichkeiten werden mit einem effizienten Integrationsschema von Bickley-Funktionen dritter Ordnung berechnet, wobei jedes Zellgebiet getrennt betrachtet wird. Die Effektivität dieser Methode wird für die irreguläre Geometrie kanadischer CANDU und CANFLEX Anlagen bewertet durch Vergleich der mit Hilfe der PIJM-Routine berechneten „grauen“ Dancoff-Faktoren mit den in der Literatur verfügbaren Werten nach der Monte-Carlo-Methode. Die Dancoff-Faktoren befinden sich bei einer Reihe verschiedener Brennstabpositionen in sehr guter Übereinstimmung mit den Werten aus der Literatur.
References
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© 2008, Carl Hanser Verlag, München
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Application of the HN method to radiative heat transfer for a non-conservative slab
- Application of the spectral Green's function method for numerically solving discrete ordinates problems in cylindrical geometry
- Chebyshev polynomial (TN) approximation to neutron transport theory and application to the critical slab problem
- Spherical albedo problem for isotropic scattering
- The slab albedo and criticality problem for the quadratic scattering kernel with the HN method
- An analytical solution for the time-dependent SN transport equation in a slab
- Deterministic calculation of grey Dancoff factors in cluster cells with cylindrical outer boundaries
- New calculations of excitation functions of some positron emitting and single photon emitting radioisotopes
- Prediction of the time-dependent failure rate for normally operating components taking into account the operational history
- Assessment of FEMAXI and TESPA-ROD codes for modelling of BDBA in RBMK-1500
- A study on the neutronic performance of the ARIES-RS fusion reactor with various coolants bearing nuclear fuel
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Application of the HN method to radiative heat transfer for a non-conservative slab
- Application of the spectral Green's function method for numerically solving discrete ordinates problems in cylindrical geometry
- Chebyshev polynomial (TN) approximation to neutron transport theory and application to the critical slab problem
- Spherical albedo problem for isotropic scattering
- The slab albedo and criticality problem for the quadratic scattering kernel with the HN method
- An analytical solution for the time-dependent SN transport equation in a slab
- Deterministic calculation of grey Dancoff factors in cluster cells with cylindrical outer boundaries
- New calculations of excitation functions of some positron emitting and single photon emitting radioisotopes
- Prediction of the time-dependent failure rate for normally operating components taking into account the operational history
- Assessment of FEMAXI and TESPA-ROD codes for modelling of BDBA in RBMK-1500
- A study on the neutronic performance of the ARIES-RS fusion reactor with various coolants bearing nuclear fuel
