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Boldt, K.R.; Kuenstler, P.A. Jr.; Schmidt, T.R.
Sandia National Labs., Albuquerque, NM (USA)1984
Sandia National Labs., Albuquerque, NM (USA)1984
AbstractAbstract
[en] The results of DCC-1 and DCC-2, the first Degraded Core Coolability experiments in the USNRC's Severe Fuel Damage Program, are presented. The experiments evaluated the coolability of a fission-heated UO2 debris bed in a water bath with pressure variable from 1 to 170 atmospheres. The 0.5-meter deep bed consisted of small-sized particulate with an average diameter of 0.4 mm for DCC-1 and large-sized particulate with an average diameter of 1.8 mm for DCC-2. DCC-1 evaluated deep bed behavior in the laminar coolability regime while DDC-2 examined coolability in the transition and turbulent flow regimes. The main results presented are the dryout heat flux dependence on pressure and the rate and method of quench of dry debris
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Source
1984; 11 p; International meeting on thermal nuclear reactor safety; Karlsruhe (Germany, F.R.); 10-14 Sep 1984; CONF-840914--12; Available from NTIS, PC A02/MF A01; 1 as DE84017004
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Report
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Conference
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ACCIDENTS, ACTINIDE COMPOUNDS, CHALCOGENIDES, ELEMENTS, ENRICHED URANIUM REACTORS, HOMOGENEOUS REACTORS, HYDRIDE MODERATED REACTORS, METALS, MIXED SPECTRUM REACTORS, OXIDES, OXYGEN COMPOUNDS, PULSED REACTORS, RARE EARTHS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, SOLID HOMOGENEOUS REACTORS, URANIUM COMPOUNDS, URANIUM OXIDES, WATER COOLED REACTORS, WATER MODERATED REACTORS
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