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AbstractAbstract
[en] This paper describes the analysis of the TMI-2 standard problem that was performed with MELCOR. The MELCOR computer code is being developed by Sandia National Laboratories for the Nuclear Regulatory Commission for the purpose of analyzing severe accidents in nuclear power plants. The primary role of MELCOR is to provide realistic predictions of severe accident phenomena and the radiological source term. The analysis of the TMI-2 standard problem allowed for comparison of the model predictions in MELCOR to plant data and to the results of more mechanistic analyses. This exercise was, therefore, valuable for verifying and assessing the models in the code. The major trends in the TMI-2 accident are reasonably well predicted with MELCOR, even with its simplified modeling. Comparison of the calculated and measured results is presented and, based on this comparison, conclusions can be drawn concerning the applicability of MELCOR to severe accident analysis
Primary Subject
Source
Weiss, A.J. (comp.) (Brookhaven National Lab., Upton, NY (USA)); Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Regulatory Research; Brookhaven National Lab., Upton, NY (United States); 578 p; Apr 1991; p. 207-230; 18. water reactor safety information meeting; Rockville, MD (United States); 22-24 Oct 1990; CONF-9010185--VOL.2; OSTI as TI91011738; NTIS; INIS; GPO
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
COMPUTER CODES, COMPUTERIZED SIMULATION, CORIUM, FISSION PRODUCT RELEASE, FUEL ELEMENT FAILURE, HEAT TRANSFER, HYDRAULICS, LOSS OF COOLANT, M CODES, MATHEMATICAL MODELS, MELTDOWN, MELTING, MOLTEN METAL-WATER REACTIONS, OXIDATION, PRESSURIZERS, PRIMARY COOLANT CIRCUITS, REACTOR ACCIDENTS, REACTOR CORE DISRUPTION, SANDIA LABORATORIES, SECONDARY COOLANT CIRCUITS, SOURCE TERMS, STEAM, THREE MILE ISLAND-2 REACTOR, TIME DEPENDENCE, TWO-PHASE FLOW, US NRC
ACCIDENTS, CHEMICAL REACTIONS, COOLING SYSTEMS, ENERGY TRANSFER, ENRICHED URANIUM REACTORS, FLUID FLOW, NATIONAL ORGANIZATIONS, PHASE TRANSFORMATIONS, POWER REACTORS, PWR TYPE REACTORS, REACTOR COMPONENTS, REACTOR COOLING SYSTEMS, REACTORS, SANDIA NATIONAL LABORATORIES, SIMULATION, THERMAL REACTORS, US AEC, US DOE, US ERDA, US ORGANIZATIONS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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