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AbstractAbstract
[en] To check containment performance of the CVTR, steam was injected above the operating floor through a 10 foot pipe cap containing the 1 inch diameter holes, at a steady rate of 102.8 lb/sec for a period of 166 seconds. This steam had an enthalpy of 1195 Btu/lb and was therefore not entirely typical of the much wetter material which would be rejected for the greater part of a true breached circuit accident. Pressure transients measured experimentally within the containment were compared with results calculated by the American code CONTEMPT and these results in turn have allowed the Winfrith code CLAPTRAP to be tested for consistency and to establish that the use of this code would have led to similar conclusions about the heat transfer coefficients at the heat absorbent surfaces. (U.K.)
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Nov 1982; 13 p
Record Type
Report
Literature Type
Numerical Data
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ACCIDENTS, ALLOYS, CARBON ADDITIONS, COMPUTER CODES, DATA, ENERGY TRANSFER, ENRICHED URANIUM REACTORS, HEAVY WATER COOLED REACTORS, HEAVY WATER MODERATED REACTORS, INFORMATION, IRON ALLOYS, IRON BASE ALLOYS, NUMERICAL DATA, PHWR TYPE REACTORS, PHYSICAL PROPERTIES, POWER REACTORS, PRESSURE TUBE REACTORS, REACTOR ACCIDENTS, REACTORS, SAFETY, SIMULATION, THERMAL REACTORS, THERMODYNAMIC PROPERTIES, TRANSITION ELEMENT ALLOYS
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