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AbstractAbstract
[en] Using a special rod built with a stack of UO2 pellets inside a thick Zircaloy clad, the authors report the measurement of the fuel-clad heat transfer coefficient when water vapour in intentionally introduced in the fuel rod at the beginning of its life. They describe the irradiation device, the measurement method (acquired data and mathematical determination of various values: temperature of the inner surface of the cladding, integrated thermal conductivity, fuel surface temperature, fuel-cladding heat transfer coefficient, thermal expansion of the cladding inner radius, UO2 thermal expansion). They finally report the experiment
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Source
Organisation for Economic Co-Operation and Development - Nuclear Energy Agency, Committee on the safety of nuclear installations - OECD/NEA/CSNI, Le Seine Saint-Germain, 12 boulevard des Iles, F-92130 Issy-les-Moulineaux (France); 774 p; 1977; p. 534-547; Specialist meeting on the behaviour of water reactor fuel elements under accident conditions; Spaatind (Norway); 13-16 Sep 1976; 3 refs.
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
ACTINIDE COMPOUNDS, ALLOYS, CHALCOGENIDES, DEPOSITION, ENERGY TRANSFER, EXPANSION, FLUIDS, FUEL ELEMENTS, GASES, INTERNATIONAL ORGANIZATIONS, OECD, OXIDES, OXYGEN COMPOUNDS, PHYSICAL PROPERTIES, REACTOR COMPONENTS, SAFETY, SIMULATION, SURFACE COATING, THERMODYNAMIC PROPERTIES, TRANSITION ELEMENT ALLOYS, URANIUM COMPOUNDS, VAPORS, ZIRCONIUM ALLOYS, ZIRCONIUM BASE ALLOYS
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