In-vessel flow characterization under severe accident conditions
Hessamodin Nourbakhsh, S.B. Kim, M. Khatib-Rahbar
Abstract
Open-access reader
Hessamodin Nourbakhsh, S.B. Kim, M. Khatib-Rahbar
Abstract
Open-access reader
The purpose of this study is to provide a parametric framework for characterization of flow and heat transfer regimes and their associated phenomenological uncertainties following severe accidents using a two dimensional, heterogenous, porous media formulation. This approach extends the understanding of buoyancy-induced flow characteristics in the uncovered region of the reactor core and the upper plenum of a PWR vessel. The results of this study can be used to augment the boil-off steam flow in integrated one-dimensional severe accident codes such as the Source Team Code Package (STCP).
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The purpose of this study is to provide a parametric framework for characterization of flow and heat transfer regimes and their associated phenomenological uncertainties following severe accidents using a two dimensional, heterogenous, porous media formulation. This approach extends the understanding of buoyancy-induced flow characteristics in the uncovered region of the reactor core and the upper plenum of a PWR vessel. The results of this study can be used to augment the boil-off steam flow in integrated one-dimensional severe accident codes such as the Source Team Code Package (STCP).
Key concepts: Plenum space, Natural circulation, Corium, Nuclear engineering, Reactor pressure vessel, Coolant, Nuclear reactor core, Nuclear reactor