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AbstractAbstract
[en] The bundles from the CORA-2 and CORA-3 Severe Fuel Damage (SFD) experiments, consisting of 9 unheated fuel rods and 16 electrically heated simulators, together with an Inconel spacer grid at middle elevation, have been evaluated on the basis of an extensive optical and SEM-analytical investigation of collected samples and selected cross sections. The results take into account measurements and visual observations during the tests as well as informations from single-effects investigations. In the present contribution the CORA-2 and CORA-3 fuel rod bundle degradation is interpreted by a short description of the pertinent phenomena, their causal mechanisms and their mutual interference. (orig./DG)
Original Title
Nachuntersuchung und Auswertung der CORA-Experimente
Primary Subject
Secondary Subject
Source
Kernforschungszentrum Karlsruhe GmbH (Germany). Projekt Nukleare Sicherheitsforschung; 270 p; Jul 1991; p. 52-58
Record Type
Report
Report Number
Country of publication
ACCIDENTS, ACTINIDE COMPOUNDS, ALLOYS, ALUMINIUM ADDITIONS, CHALCOGENIDES, CHROMIUM ADDITIONS, CHROMIUM ALLOYS, CORROSION RESISTANT ALLOYS, ENRICHED URANIUM REACTORS, FUEL ASSEMBLIES, FUEL ELEMENTS, HEAT RESISTING ALLOYS, INCONEL ALLOYS, IRON ADDITIONS, IRON ALLOYS, MOLYBDENUM ALLOYS, NICKEL ALLOYS, NICKEL BASE ALLOYS, NIOBIUM ALLOYS, OXIDES, OXYGEN COMPOUNDS, POWER REACTORS, REACTOR ACCIDENTS, REACTOR COMPONENTS, REACTORS, THERMAL REACTORS, TIN ALLOYS, TITANIUM ADDITIONS, URANIUM COMPOUNDS, URANIUM OXIDES, WATER COOLED REACTORS, WATER MODERATED REACTORS, ZIRCALOY, ZIRCONIUM ALLOYS, ZIRCONIUM BASE ALLOYS
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