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Powers, D.A.; Bradley, D.R.; Brockmann, J.E.; Copus, E.R.; Greene, G.A.; Burson, S.B.
Sandia National Labs., Albuquerque, NM (USA)1989
Sandia National Labs., Albuquerque, NM (USA)1989
AbstractAbstract
[en] The need for improved models of core debris interactions with concrete has been met by several computer codes. In this paper, the status of validation of one of these codes, CORCON, will be discussed. The phenomenon that the CORCON code and the other core debris/concrete interactions codes attempt to model is the thermal attack on concrete by an internally heated, chemically reacting, molten mixture of metals (steel and unoxidized zirconium cladding) and oxides (UO2 and ZrO2, predominantly). Two key features of the models that must be validated if confidence is to be placed in the model predictions are the (1) heat transfer from core debris, and (2) heat generation especially that caused by chemical reactions. A third key feature, the release of radionuclides during core debris/concrete interactions, is not explicitly addressed in this paper. 23 refs., 6 figs
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1989; 11 p; Seminar on fission product transport processes in reactor accidents; Dubrovnik (Yugoslavia); 22-26 May 1989; CONF-890546--6; Available from NTIS, PC A03/MF A01 - OSTI; 1 as DE89011882; Portions of this document are illegible in microfiche products.
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Report
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Conference
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ACCIDENTS, ACTINIDE COMPOUNDS, BUILDING MATERIALS, CARBON COMPOUNDS, CARBON OXIDES, CHALCOGENIDES, COMPUTER CODES, ELEMENTS, ENERGY TRANSFER, MATERIALS, NONMETALS, NUCLEAR FACILITIES, OXIDES, OXYGEN COMPOUNDS, POWER PLANTS, REACTOR ACCIDENTS, REACTOR COMPONENTS, SAFETY, THERMAL POWER PLANTS, TRANSITION ELEMENT COMPOUNDS, URANIUM COMPOUNDS, URANIUM OXIDES, ZIRCONIUM COMPOUNDS
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