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Unsteady single phase natural circulation flow mixing prediction using 3D thermal-hydraulic system and CFD codes
Advanced 3D computational tools are increasingly used to simulate complex phenomena occurring during scenario involving operational transients and accidents in nuclear power plants. Among these scenarios, one can mention the asymmetric coolant mixing under natural circulation flow regimes. This issue motivated some detailed experimental investigations carried out within the OECD/NEA PKL projects. The aim of these investigations was, besides the assessment of the mixing phenomenon in the reactor pressure vessel, to provide experimental data for computer code validations. In the current study, the ROCOM/PKL-3 T2.3 experimental test is assessed using on one hand thermal-hydraulic system codes with 3D capabilities, and on the other hand a CFD computational tool. The results emphasize the capabilities and the differences between the considered computational tools as well as their suitability for such purposes.
Nuclear Technology 203(2018), 293-314
- Final Draft PDF 145 kB Secondary publication