Local heat transfer coefficient near the spacer grids
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B. Cesna
Abstract
The paper presents the experimental data of the local heat transfer in the fuel rod assembly with honeycomb type spacer grids. It was established experimentally that the separation of the boundary layer behind the spacer grid increases the interchannel coefficient of transverse mixing of flow, and therefore, the local heat transfer. If the distance between the spacer grids is relatively small, they influence one another through the redistribution of mass flow in elementary channels. The local heat transfer behind the spacer grid varies with a distance from it. The local heat transfer can be determined within ±3% using similar equations for any elementary cell.
Kurzfassung
In diesem Beitrag werden die experimentellen Ergebnisse der lokalen Wärmeübertragung in einer Brennelementanordnung mit wabenförmigen Abstandsgittern vorgestellt. Es zeigte sich, dass die Abtrennung der Grenzschicht hinter den Abstandsgittern den transversalen Mischungskoeffizienten einer Strömung zwischen den Kanälen erhöht und deshalb auch die lokale Wärmeübertragung. Wenn der Abstand zwischen den Abstandsgittern verhältnismäßig klein ist, so beeinflussen sich die Abstandsgitter gegenseitig über die Umverteilung des Massenstroms in den elementaren Kanälen. Die lokale Wärmeübertragung hinter dem Abstandsgitter verändert sich in Abhängigkeit vom Abstand. Die lokale Wärmeübertragung kann mit einer Genauigkeit von ±3% für jede beliebige elementare Zelle mit Hilfe ähnlicher Gleichungen berechnet werden.
References
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© 2011, Carl Hanser Verlag, München
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- Summaries
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- Novel method to produce 109Cd via proton irradiation of electroplated silver on a gold-coated copper backing
- Technical Notes/Technische Mitteilungen
- Atmospheric dispersion of accidental release of radioactive gases from high enriched and low enriched fuel of Miniature Neutron Source Reactors (MNSR)
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Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Stress analyses for reactor pressure vessels by the example of a product line '69 Boiling Water Reactor
- Multiple condensation induced water hammer events, experiments and theoretical investigations
- Simulation of load following mode of operation for a natural circulation pressure tube type BWR
- CANDU fuel elements behaviour in the load following tests
- Local heat transfer coefficient near the spacer grids
- Best estimate analysis of PHEBUS FPT1 experiment bundle phase using ASTEC code ICARE module
- Investigations of bi-directional flow behaviour in presence of a large vertical opening in a fire compartment
- CANDU reactors with reactor grade plutonium/thorium carbide fuel
- Novel method to produce 109Cd via proton irradiation of electroplated silver on a gold-coated copper backing
- Technical Notes/Technische Mitteilungen
- Atmospheric dispersion of accidental release of radioactive gases from high enriched and low enriched fuel of Miniature Neutron Source Reactors (MNSR)
- Fuel burnup of modified fuel assembly configurations for a small medical reactor
- Determination of natural uranium, thorium and radium isotopes in water and soil samples by alpha spectroscopy
