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Chung, H.M.; Thomas, G.R.
Proceedings of the workshop on the impact of hydrogen on water reactor safety. Volume II of IV1981
Proceedings of the workshop on the impact of hydrogen on water reactor safety. Volume II of IV1981
AbstractAbstract
[en] Zircaloy-4 oxidation rates have been measured in hydrogen-steam mixtures at 1375 and 15000C for various hydrogen-to-total pressure ratios. For ratios of greater than or equal to 0.5, the oxide-layer growth rate and specimen weight gain decrease as the hydrogen content in the gas mixture increases, which implies a similar dependence for the reaction-heat-generation rate. Implications of the results for core heatup and damage have been evaluated, assuming a scenario of significant hydrogen fraction in the boundary layer of fuel rod and coolant for the upper region of the Three Mile Island-2 Reactor (TMI-2) core during the uncovery period of 100 to 174 min after the turbine trip. Analysis shows that the slower oxidation and core-heatup rates in the hydrogen-steam mixture imply significantly lower peak cladding temperature and less UO2 liquefaction for the TMI-2 fuel rods than indicated from the previous calculations
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Source
Berman, M. (ed.); Sandia National Labs., Albuquerque, NM (USA); p. 36-65; Sep 1981; p. 36-65; Workshop on the impact of hydrogen on water reactor safety; Albuquerque, NM (USA); 26-28 Jan 1981; Available from NTIS, PC A12/MF A01; 1 - GPO as DE83003259
Record Type
Report
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Conference
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ALLOY-ZR98SN-4, CHEMICAL REACTION KINETICS, EUTECTICS, FUEL CANS, FUEL RODS, FUEL-CLADDING INTERACTIONS, HELIUM GENERATION, HYDROGEN, HYDROGEN GENERATION, LOSS OF COOLANT, MECHANICAL FRAGMENTATION, OXIDATION, REACTION HEAT, REACTOR ACCIDENTS, REACTOR COOLING SYSTEMS, REACTOR CORES, REACTOR MATERIALS, STEAM, THREE MILE ISLAND-2 REACTOR, URANIUM DIOXIDE, VERY HIGH TEMPERATURE
ACCIDENTS, ACTINIDE COMPOUNDS, ALLOYS, CHALCOGENIDES, CHEMICAL REACTIONS, CHROMIUM ADDITIONS, COOLING SYSTEMS, CORROSION RESISTANT ALLOYS, ELEMENTS, ENRICHED URANIUM REACTORS, ENTHALPY, FUEL ELEMENTS, HEAT RESISTING ALLOYS, IRON ADDITIONS, KINETICS, MATERIALS, NONMETALS, OXIDES, OXYGEN COMPOUNDS, PHYSICAL PROPERTIES, PHYSICAL RADIATION EFFECTS, POWER REACTORS, PWR TYPE REACTORS, RADIATION EFFECTS, REACTION KINETICS, REACTOR COMPONENTS, REACTORS, THERMAL REACTORS, THERMODYNAMIC PROPERTIES, TIN ALLOYS, URANIUM COMPOUNDS, URANIUM OXIDES, WATER COOLED REACTORS, WATER MODERATED REACTORS, ZIRCALOY, ZIRCONIUM ALLOYS, ZIRCONIUM BASE ALLOYS
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