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Anis Bousbia Salah,Jacques Vlassenbroeck 한국원자력학회 2017 Nuclear Engineering and Technology Vol.49 No.3
Coolant mixing under natural circulation flow regime constitutes a key parameter that mayplay a role in the course of an accidental transient in a nuclear pressurized water reactor. This issue has motivated some experimental investigations carried out within the OECD/NEA PKL projects. The aim was to assess the coolant mixing phenomenon in the reactorpressure vessel downcomer and the core lower plenum under several asymmetric steadyand unsteady flow conditions, and to provide experimental data for code validations. Formerstudies addressed the mixing phenomenon using, on the one hand, one-dimensionalcomputational approaches with cross flows that are not fully validated under transientconditions and, on the other hand, expensive computational fluid dynamic tools thatare not always justified for large-scale macroscopic phenomena. In the current framework,an unsteady coolant mixing experiment carried out in the Rossendorf coolant mixingtest facility is simulated using the three-dimensional porous media capabilities ofthe thermalehydraulic system CATHARE code. The current study allows highlighting thecurrent capabilities of these codes and their suitability for reproducing the main phenomenaoccurring during asymmetric transient natural circulation mixing conditions.
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