Adaptation of the FEMAXI-6 code and RBMK fuel rods model testing employing the best estimate approach
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A. Marao
Abstract
This paper provides information about the possibility to apply the FEMAXI-6 code for RBMK-1500 reactors. New thermal properties and correlations responsible for thermal analysis (thermal conductivity and heat capacity) according to RBMK-1500 specification were included into the FEMAXI-6 code. The RBMK-1500 fuel rod model using the adapted FEMAXI-6 code was developed and tested by employing uncertainty and sensitivity analysis. The processes in fuel rods during normal plant operation were modelled. The results received were compared with calculations performed by specialists from the Kurchatov Institute (designers of RBMK). The reasonable agreement of both calculation results shows that the adapted FEMAXI-6 code and the developed model are suitable for future analysis of processes in fuel rods of RBMK-1500 reactors. Also this work demonstrates what sensitivity and uncertainty analysis can be used for the model development.
Kurzfassung
In diesem Beitrag werden die Anwendungsmöglichkeiten des FEMAXI-6-Codes für den Reaktortyp RBMK-1500 dargestellt. Die für die Anlage RBMK-1500 spezifischen thermischen Eigenschaften und Abhängigkeiten, (Wärmeleitfähigkeit und Wärmekapazität) wurden im FEMAXI-6-Code berücksichtigt. Unter Verwendung des angepassten FEMAXI-6-Codes wurde ein Brennelement-Modell für den Reaktor vom Typ RBMK-1500 entwickelt und unter Berücksichtigung von Unsicherheits- und Sensitivitätsanalysen getestet. Die Prozesse in den Brennelementen während des Normalbetriebs der Anlage wurden modelliert. Die erzielten Ergebnisse wurden mit den Berechnungen des Kurtchatov-Instituts (zuständig für die Auslegung von RBMK-Reaktoren) verglichen. Die entsprechende Übereinstimmung der Rechenergebnisse zeigt, dass der angepasste FEMAXI-6-Code und das entwickelte Modell für weitere Analysen von Prozessen in den Brennelementen von RBMK-1500 geeignet sind. Weiterhin wird in diesem Beitrag gezeigt, dass Unsicherheits- und Sensitivitätsanalysen für die Modell–Entwicklung verwendet werden können.
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© 2010, Carl Hanser Verlag, München
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Adaptation of the FEMAXI-6 code and RBMK fuel rods model testing employing the best estimate approach
- In-reactor measurements of fuel centerline temperature variation during power change
- Pertinence of tests used for conformity assessments of fire resistance of nuclear power plant components – opinion of several institutions in Europe
- Analysis of the instability of OTSG of movable nuclear power devices by using the multivariable frequency domain method
- Steady state thermal hydraulic calculations for MTR plate-type research reactors
- Production cross sections of medical 110,111In radionuclides
- Nuclear level density parameters of some largely deformed nuclei of medical radionuclides in low-lying collective excitation modes
- A discrete ordinates operator for the diffuse transmission of a mixed neutron beam through a multilayered medium
- Kritikalitätssicherheit der Endlagerung ausgedienter Kernbrennstoffe
- Technical Notes/Technische Mitteilungen
- Methods for thin foil thickness determination by using alpha spectroscopy
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Adaptation of the FEMAXI-6 code and RBMK fuel rods model testing employing the best estimate approach
- In-reactor measurements of fuel centerline temperature variation during power change
- Pertinence of tests used for conformity assessments of fire resistance of nuclear power plant components – opinion of several institutions in Europe
- Analysis of the instability of OTSG of movable nuclear power devices by using the multivariable frequency domain method
- Steady state thermal hydraulic calculations for MTR plate-type research reactors
- Production cross sections of medical 110,111In radionuclides
- Nuclear level density parameters of some largely deformed nuclei of medical radionuclides in low-lying collective excitation modes
- A discrete ordinates operator for the diffuse transmission of a mixed neutron beam through a multilayered medium
- Kritikalitätssicherheit der Endlagerung ausgedienter Kernbrennstoffe
- Technical Notes/Technische Mitteilungen
- Methods for thin foil thickness determination by using alpha spectroscopy