Modeling and Visualization of Coolant Flow in a Fuel Rod Bundle of a Small Modular Reactor
Sergei Dmitriev,
Tatiyana Demkina,
Aleksandr Dobrov,
Denis Doronkov,
Daniil Kuritsin,
Danil Nikolaev,
Alexey Pronin,
Anton Riazanov,
Dmitriy Solntsev
Affiliations
Sergei Dmitriev
The Department of the Nuclear and Thermal Power Stations, Institute of Nuclear Power Engineeniring and Applied Physics n.a. Academican F.M. Mitenkov, Nizhny Novgorod State Technical University n.a. R.E. Alekseev, 603950 Nizhny Novgorod, Russia
Tatiyana Demkina
The Department of the Nuclear and Thermal Power Stations, Institute of Nuclear Power Engineeniring and Applied Physics n.a. Academican F.M. Mitenkov, Nizhny Novgorod State Technical University n.a. R.E. Alekseev, 603950 Nizhny Novgorod, Russia
Aleksandr Dobrov
The Department of the Nuclear and Thermal Power Stations, Institute of Nuclear Power Engineeniring and Applied Physics n.a. Academican F.M. Mitenkov, Nizhny Novgorod State Technical University n.a. R.E. Alekseev, 603950 Nizhny Novgorod, Russia
Denis Doronkov
The Department of the Nuclear and Thermal Power Stations, Institute of Nuclear Power Engineeniring and Applied Physics n.a. Academican F.M. Mitenkov, Nizhny Novgorod State Technical University n.a. R.E. Alekseev, 603950 Nizhny Novgorod, Russia
Daniil Kuritsin
The Department of the Nuclear and Thermal Power Stations, Institute of Nuclear Power Engineeniring and Applied Physics n.a. Academican F.M. Mitenkov, Nizhny Novgorod State Technical University n.a. R.E. Alekseev, 603950 Nizhny Novgorod, Russia
Danil Nikolaev
The Department of the Nuclear and Thermal Power Stations, Institute of Nuclear Power Engineeniring and Applied Physics n.a. Academican F.M. Mitenkov, Nizhny Novgorod State Technical University n.a. R.E. Alekseev, 603950 Nizhny Novgorod, Russia
Alexey Pronin
The Department of the Nuclear and Thermal Power Stations, Institute of Nuclear Power Engineeniring and Applied Physics n.a. Academican F.M. Mitenkov, Nizhny Novgorod State Technical University n.a. R.E. Alekseev, 603950 Nizhny Novgorod, Russia
Anton Riazanov
The Department of the Nuclear and Thermal Power Stations, Institute of Nuclear Power Engineeniring and Applied Physics n.a. Academican F.M. Mitenkov, Nizhny Novgorod State Technical University n.a. R.E. Alekseev, 603950 Nizhny Novgorod, Russia
Dmitriy Solntsev
The Department of the Nuclear and Thermal Power Stations, Institute of Nuclear Power Engineeniring and Applied Physics n.a. Academican F.M. Mitenkov, Nizhny Novgorod State Technical University n.a. R.E. Alekseev, 603950 Nizhny Novgorod, Russia
This article presents the results of an experimental study of the coolant flow in a fuel rod bundle of a nuclear reactor fuel assembly of a small modular reactor for a small ground-based nuclear power plant. The aim of the work is to experimentally determine the hydrodynamic characteristics of the coolant flow in a fuel rod bundle of a fuel assembly. For this purpose, experimental studies were conducted in an aerodynamic model that included simulators of fuel elements, burnable absorber rods, spacer grids, a central displacer, and stiffening corners. During the experiments, the water coolant flow was modeled using airflow based on the theory of hydrodynamic similarity. The studies were conducted using the pneumometric method and the contrast agent injection method. The flow structure was visualized by contour plots of axial and tangential velocity, as well as the distribution of the contrast agent. During the experiments, the features of the axial flow were identified, and the structure of the cross-flows of the coolant was determined. The database obtained during the experiments can be used to validate CFD programs, refine the methods of thermal-hydraulic calculation of nuclear reactor cores, and also to justify the design of fuel assemblies.
