作者: Arun Kumar Nayak , Raj Kumar Singh , Parimal P. Kulkarni , Bal Raj Sehgal
DOI: 10.1016/J.NUCENGDES.2009.02.016
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摘要: During a postulated severe accident, the core can melt and fail reactor vessel. Subsequently, molten corium be relocated in containment cavity forming pool. The pool flooded with water at top for quenching it. However, question that arises is to what extent ingress cool quench To reveal that, numerical study has been carried out using computer code MELCOOL considers heat transfer behaviour axial radial directions from overlaying water, crust generation growth, thermal stresses built-in crust, disintegration of into debris, natural convection debris ingression bed. validate code, experiments were conducted facility named as coolability (COMECO). consists test section (200 mm x 200 square cross-section) height 300 mm. About 14 L comprising 30% CaO + 70% B2O3 (by wt.) was poured section. heated by four heaters outside simulate decay corium. top, depth kept constant around 700 throughout experiment. transient temperature different locations measured 24 K-type thermocouples steam flow rate vortex meter. measurements indicated could only up certain predictions compared data distribution inside found quite well.