22 results on '"Papukchiev, Angel"'
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2. Validation of coupled ATHLET-OpenFOAM simulation on a large-scale single- and two-phase flow experiment
3. The 34th German CFD network of competence meeting: numerical 3D simulation of reactor primary cooling circuit and containment flows
4. Application of the coupled code ATHLET-ANSYS CFX for the simulation of the flow mixing inside the ROCOM test facility
5. On the need for conjugate heat transfer modeling in transient CFD simulations
6. The European GO-VIKING project on flow-induced vibrations: overview and current status.
7. Uncertainty and sensitivity analysis of coupled multiscale simulations in the context of the SESAME EU-Project
8. Numerical analysis of reactor relevant vibrations using advanced multiphysics CFD-CSM methods
9. GRS contributions to flow-induced vibrations related activities in Europe
10. The 33rd German CFD Network of Competence Meeting: 20 years of advances in the numerical 3D simulation of reactor relevant flows
11. Advanced multi-physics simulation for reactor safety in the framework of the NURESAFE project
12. Development and application of computational fluid dynamics approaches within the European project THINS for the simulation of next generation nuclear power systems
13. Comparison of different coupling CFD–STH approaches for pre-test analysis of a TALL-3D experiment
14. Experimental Validation of ANSYS CFX for Transient Flows With Heat Transfer in a Tubular Heat Exchanger
15. Experimental Validation of ANSYS CFX for Transient Flows With Heat Transfer in a Tubular Heat Exchanger
16. Blind Simulations of NACIE-UP Experimental Tests by STH Codes
17. Methoden zur Optimierung der Kernauslegung von Druckwasserreaktoren mit reduziertem Borsäureeinsatz
18. A New Data-Driven ATHLET – ANSYS CFD Coupling Method for Efficient Simulation of Nuclear Power Plant Circuits
19. Extension and Application of the Coupled 1D-3D Thermal-Hydraulic Code ATHLET-ANSYS CFX for the Simulation of Liquid Metal Coolant Flows in Advanced Reactor Concepts
20. Assessment of the Design and Safety Properties of PWR Cores With Reduced Soluble Boron Utilization
21. ICONE15-10398 INFLUENCE OF BORON REDUCTION STRATEGIES ON PWR ACCIDENT MANAGEMENT FLEXIBILITY
22. Influence of Low Boron Core Design on PWR Transient Behavior
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