Improved Dancoff factors for cluster fuel bundles by the WIMSD code
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S. Q. Bogado Leite
Abstract
The recently developed tracking routine PIJM, for computing improved two-dimensional first-flight collision matrices for the WIMSD code, has been modified to evaluate black Dancoff factors for cluster fuel bundles in unit cells with cylindrical outer boundaries. The routine, similar to the original PIJ but employing an efficient in-plane integration scheme of the Bickley functions appearing in those expressions, is first compared with the accurate Carlvik method in the calculation of Dancoff factors for regular lattices, both with and without a gap surrounding the fuel rods. Dancoff factors for the more general cases of CANDU37 and CANFLEX fuel bundles are next obtained and compared with Monte Carlo based calculations, illustrating the accuracy of the proposed scheme.
Kurzfassung
Das kürzlich entwickelte Modul PIJM des Codes WIMSD zur Berechnung von “first flight” Stoßwahrscheinlichkeiten wurde modifiziert zur Auswertung schwarzer Dancoff-Faktoren für Cluster Brennelementbündel in zwei-dimensionalen zylindrischen Einheitszellen. Das Modul, das zusätzlich zum Original PIJ eine effizientere Integrationstechnik der Bickley Funktionen beinhaltet, wird zuerst verglichen mit der genauen Carlvik Methode bei der Berechnung von Dancoff Faktoren für normale Gitterstruktur der Brennelemente, mit und ohne Spalt um die Brennstäbe. Als nächstes werden Dancoff Faktoren für CANDU37 und CANFLEX Brennelementbündel berechnet und verglichen mit Ergebnissen auf der Basis von Monte Carlo Berechnungen, um so die Genauigkeit des vorgeschlagenen Verfahrens zu zeigen.
References
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© 2004, Carl Hanser Verlag, München
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Improved Dancoff factors for cluster fuel bundles by the WIMSD code
- The impact of non-optimized operation of nuclear power plants on the nuclear fuel burn-up
- Experience with MTR fuel at the HOR reactor
- Comparison of two modern approaches for MBDA calculations of RBMK-type reactors
- Calculation of the energy deposition in the targets from C to U irradiated with intermediate energy protons
- U-Pb accelerator-driven sub-critical systems research at the proton beam of the JINR NUCLOTRON
- Steady state thermal-hydraulic analysis for the ETRR-2 Research Reactor
- Monte Carlo simulation of the ETRR-2 research reactor using the MCNP Code
- Preliminary evaluation of the fixed and fluidized bed nuclear reactor concept using the IAEA-INPRO methodology
- Technical Notes/Technische Mitteilungen
- A clean nuclear blasting technique for the excavation of a new isthmus canal in Central America
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Improved Dancoff factors for cluster fuel bundles by the WIMSD code
- The impact of non-optimized operation of nuclear power plants on the nuclear fuel burn-up
- Experience with MTR fuel at the HOR reactor
- Comparison of two modern approaches for MBDA calculations of RBMK-type reactors
- Calculation of the energy deposition in the targets from C to U irradiated with intermediate energy protons
- U-Pb accelerator-driven sub-critical systems research at the proton beam of the JINR NUCLOTRON
- Steady state thermal-hydraulic analysis for the ETRR-2 Research Reactor
- Monte Carlo simulation of the ETRR-2 research reactor using the MCNP Code
- Preliminary evaluation of the fixed and fluidized bed nuclear reactor concept using the IAEA-INPRO methodology
- Technical Notes/Technische Mitteilungen
- A clean nuclear blasting technique for the excavation of a new isthmus canal in Central America
