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Sharon, A.; Ellison, P.G.; Henry, R.E.; Kenton, M.A.; Hammersley, R.J.
EG and G Idaho, Inc., Idaho Falls, ID (USA)1988
EG and G Idaho, Inc., Idaho Falls, ID (USA)1988
AbstractAbstract
[en] When core material reaches melting conditions severe degradation of the core geometry occurs. Data available on the core behavior in a severely degraded state suggest that extensive blockage of the flow channels would occur. If a sufficient bypass is available for the gas flow, such as in the LOFT LP-FP-2 test, severe retardation of the hydrogen and fission product sources from the degraded channel is suggested from the available data. This phenomena is expected to occur in an LWR core and should be considered by core models that are used for severe accident analysis. In the MAAP code it is done by preventing gas flow through molten core regions. Good agreement is obtained with all relevant data that are directly applicable to LWR accident conditions. A more mechanistic model for the freezing of core material and its effect on the coolant channel geometry is currently being investigated by the US Department of Energy Advanced Reactor Severe Accident Program (ARSAP). 8 refs., 2 figs
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1988; 8 p; International symposium on severe accidents in nuclear power plants IAEA - OECD/NEA; Sorrento (Italy); 21-25 Mar 1988; CONF-880309--8; IAEA-SM--296/80; CONTRACT AC07-76ID01570; Available from NTIS, PC A02/MF A01 as DE90001999; OSTI; INIS; US Govt. Printing Office Dep
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Report
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Conference
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BWR TYPE REACTORS, COMPARATIVE EVALUATIONS, COMPUTERIZED SIMULATION, CORIUM, DEFORMATION, FISSION PRODUCT RELEASE, FISSION PRODUCTS, FUEL ELEMENTS, HEAT TRANSFER, HYDRAULICS, LOFT REACTOR, LOSS OF COOLANT, M CODES, MELTDOWN, PWR TYPE REACTORS, REACTOR CHANNELS, REACTOR COOLING SYSTEMS, REACTOR CORES, REACTOR SAFETY, SCALE MODELS
ACCIDENTS, COMPUTER CODES, COOLING SYSTEMS, ENERGY TRANSFER, ENRICHED URANIUM REACTORS, EVALUATION, ISOTOPES, MATERIALS, POWER REACTORS, RADIOACTIVE MATERIALS, REACTOR ACCIDENTS, REACTOR COMPONENTS, REACTORS, RESEARCH AND TEST REACTORS, SAFETY, SIMULATION, STRUCTURAL MODELS, TANK TYPE REACTORS, TEST FACILITIES, TEST REACTORS, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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