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AbstractAbstract
[en] The phenomena addressed in this lecture are: in-vessel and ex-vessel hydrogen generation; in-vessel and in-containment natural circulation, steam explosions, direct containment heating, core-concrete interaction; debris coolability, containment strength/failure. The following events were modeled: axial and radial power distribution, two-phase level in the core, steam generation in covered section, decay heat generation, convection to gas, cladding oxidation, cold ballooning and rupture, natural circulation between the core and upper plenum, hydrogen generation, core meltdown, reflooding. Differences between PWR and BWR type reactors
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Source
Westinghouse Nuclear Technology Systems, Westinghouse Energy Systems International, Fauske and Associates, Inc., Brussels (Belgium); 561 p; 2004; [189 p.]; Light water reactor severe accident seminar; Brussels (Belgium); 16-18 May 1988; Figs, tabs
Record Type
Report
Literature Type
Conference
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ACCIDENTS, CONTAINMENT, CONVECTION, DEPOSITION, ECCS, ENERGY TRANSFER, ENGINEERED SAFETY SYSTEMS, ENRICHED URANIUM REACTORS, FLUID FLOW, HEAT TRANSFER, MASS TRANSFER, PHYSICAL RADIATION EFFECTS, POWER REACTORS, RADIATION EFFECTS, REACTOR ACCIDENTS, REACTOR PROTECTION SYSTEMS, REACTORS, SURFACE COATING, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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