Neutronic calculations for the new fuel configuration of the ETRR-1 research reactor
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M. Aziz
Abstract
Neutronic calculations were performed for the new loading configuration of the ETRR-1 research reactor. The MCNP three dimensions Monte Carlo code and the two dimensions CITATION code are used to model the reactor. The power and thermal flux distributions in the reactor core are calculated. The power peak factor and the effect of control rod insertion on both flux and power profiles in the reactor core are determined and analyzed. The partial and total control rods worth are calculated. It was found that the difference between MCNP and CITATION in power distributions is 4 to 8 % and for thermal flux ranges between 3 to 14 %.
Kurzfassung
Für die neue Brennstabanordnung des ETRR-1 Forschungsreaktors wurden Neutronenphysikalische Berechnungen durchgeführt. Der dreidimensionale MCNP Monte Carlo Code und der zweidimensionale CITATION Code wurden zur Modellierung des Reaktors verwendet. Die Leistungs- und Flussverteilung im Reaktorkern wurden berechnet. Die maximalen Leistungswerte und die Wirkung bei Einführung des Steuerstabs auf die Verteilung des thermischen Neutronenflusses und die Leistung im Reaktorkern wurden bestimmt und analysiert. Lokale und gesamte Steuerstabwirksamkeit wurden berechnet. Der Unterschied zwischen den Ergebnissen der MCNP- und der CITATION-Berechnungen liegt bei den Leistungsverteilungen zwischen 4 und 8% und beim Neutronenfluss zwischen 3 und 14 %.
References
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© 2005, Carl Hanser Verlag, München
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Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries/Kurzfassungen
- Technical Contributions/Fachbeiträge
- Integrated management systems in the nuclear field
- Phenomenological model for non-equilibrium deuteron emission in nucleon induced reactions
- Best estimate analysis of group distribution header blockage events in RBMK-1500 reactors
- Simulation of the hydrogen distribution in the confinement of the Ignalina nuclear power plant
- Neutronic calculations for the new fuel configuration of the ETRR-1 research reactor
- Design stability and safety margins of the ETRR-2 core cooling system regarding seismic loads
- Thermal-hydraulic assessment of topaz irradiation processes at the ETRR-2 research reactor
- The HN method for slab albedo problem for linearly anisotropic scattering
- On the plane-wave theory in fertile uranium
- Safety and security of radioactive sources – international provisions
- The singular eigenfunction method: the critical slab problem for linearly anisotropic scattering
- Technical Notes/Technische Mitteilungen
- Results of in vitro intercomparison tests of the Coordinating Office on Incorporation Monitoring in Germany
