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AbstractAbstract
[en] 1 - Description of test facility: The Integral Experiments are designed to follow the behaviour of a reactor system in various off-normal or accident conditions. The ITD matrix data is suitable for the validation of best estimate thermal-hydraulic computer codes: it consists of phenomenologically well founded experiments, for which comparison of the measured and calculated parameters forms a basis for establishing the accuracy of the test predictions. 2 - Description of test: A - Test types for PWRs: -Test types related to large break LOCAs: Blowdown phase, Refill phase, Reflood phase. - Test types related to small break LOCAs: Stationary test addressing energy transport on primary side, Stationary test addressing energy transport on secondary side, Small break overfeed by HPIS, secondary side necessary, Small break w/o HPIS overfeeding, secondary side necessary, Intermediate break, secondary side not necessary, Pressurizer leaks, Steam generator tube rupture (SGTR). - Test types related to small and intermediate breaks in PWRs with OTSGs - Test types related to transients: Anticipated Transient Without Scram (ATWS), Loss of feedwater, non ATWS, Loss of heat sink, non ATWS, Station blackout, Steam line break, Feed line break, Reactivity disturbance, Overcooling. - Test types related to transients at shutdown conditions: Loss of RHR at mid-loop operation with no or small openings, Loss of RHR at mid-loop operation with large openings, Loss of RHR at mid-loop operation with a dam in a hot leg, Boron dilution at shutdown, Cold overpressure transients at shutdown. - Test types related to Accident Management: High pressure primary side feed and bleed, Low pressure primary side feed and bleed, Secondary side feed and bleed, RCP restart in a highly voided primary system, Primary to secondary leak with multiple failures. B - Test types related to BWRs: - Test types for LOCA: Large steam line break with fast depressurization, Large break below water level with fast depressurization, Small break without depressurization before ADS Actuation, Intermediate break with slow depressurization, Spray line break, Refill - reflood. - Test types for transients: Stationary test measuring power flow map, Recirculation pump trip, Core stability, Loss of main heat sink, Feedwater flow or temperature disturbance, e.g. LOFW, Loss of feedwater (LOFW) up to time of constant pressure, Inadvertent increase in steam flow, ATWS, Station blackout (Loss of offsite power)
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Source
5 Nov 1997; [html]; Available on-line: http://www.nea.fr/abs/html/csni0000.html; Country of input: International Atomic Energy Agency (IAEA); 1 ref.
Record Type
Miscellaneous
Country of publication
ACCIDENTS, BOILERS, COOLING SYSTEMS, DESIGN BASIS ACCIDENTS, ENERGY SYSTEMS, ENRICHED URANIUM REACTORS, FAILURES, FLUID MECHANICS, HYDRAULICS, HYDROGEN COMPOUNDS, MANAGEMENT, MECHANICS, OXYGEN COMPOUNDS, PIPELINES, POWER REACTORS, REACTOR ACCIDENTS, REACTOR COMPONENTS, REACTOR COOLING SYSTEMS, REACTOR SHUTDOWN, REACTORS, REMOVAL, SAFETY, SHUTDOWN, SIMULATION, SINKS, THERMAL REACTORS, VAPOR GENERATORS, WATER, WATER COOLED REACTORS, WATER MODERATED REACTORS
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