Authors & Affiliations

Dmitriev S.M., Dobrov A.A., Doronkov D.V., Khrobostov A.E., Pronin A.N., Ryazanov A.V., Sorokin V.D., Yudin A.V.
Nizhniy Novgorod State Technical University n.a. R.E. Alekseev, Nizhniy Novgorod, Russia

Dmitriev S.M. – Rector, Dr. Sci.(Tech.), Professor, Institute of Nuclear Power Engineering and Technical Physics, Nizhny Novgorod State Technical University. R.E. Alekseeva.
Dobrov A.A. – Senior Lecturer, Institute of Nuclear Power Engineering and Technical Physics, Nizhny Novgorod State Technical University. R.E. Alekseeva.
Doronkov D.V. – Senior Lecturer, Institute of Nuclear Power Engineering and Technical Physics, Nizhny Novgorod State Technical University. R.E. Alekseeva.
Khrobostov A.E. – Director, Cand. Sci. (Tech.), Institute of Nuclear Power Engineering and Technical Physics, Nizhny Novgorod State Technical University. R.E. Alekseeva.
Pronin A.N. – Senior Lecturer, Institute of Nuclear Power Engineering and Technical Physics, Nizhny Novgorod State Technical University. R.E. Alekseeva.
Ryazanov A.V. – Engeneer of the 2nd category, Institute of Nuclear Power Engineering and Technical Physics, Nizhny Novgorod State Technical University. R.E. Alekseeva. Contacts: 24, Minina st., Nizhny Novgorod, Russia, 603155. Tel.: +7(831)436-80-17; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Sorokin V.D. – Engeneer, Institute of Nuclear Power Engineering and Technical Physics, Nizhny Novgorod State Technical University. R.E. Alekseeva.
Yudin A.V. – Masters student, Institute of Nuclear Power Engineering and Technical Physics, Nizhny Novgorod State Technical University. R.E. Alekseeva.

Abstract

The article presents the results of experimental studies of the influence of various designs of the mixing grids on the coolant flow into the PWR. The studies were carried out by simulating coolant flow in the core at a research air test facility, which is an aerodynamic open circuit. Special pneumometric sensors were used to measure the local hydrodynamic characteristics of the flow. These sensors make it possible to measure the velocity vector and the value of the flow velocity. During experimental studies of the local hydrodynamics of coolant, transverse flow rates, as well as the coolant flow rates in the cells of the test TVS-KVADRAT model were measured. The analysis of the spatial distribution of absolute flow velocity projections made it possible to study and detail the flow pattern of the coolant behind the mixing grids with different types of deflectors. The accumulated database about the flow of coolant into the TVS-KVADRAT is the basis of the engineering justification for the construction of the fuel assemblies for core of the PWR. The results of experimental studies are used to verify CFD codes, both foreign and domestic development, as well as programs for detailed zone calculation of reactor cores with a view to reducing conservatism in justifying the thermal engineering reliability of reactor units.

Keywords
nuclear reactor, active zone, fuel assembly, fuel rod, mixing grid, hydrodynamics of coolant

Article Text (PDF, in Russian)

References

UDC 621.029

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants", 2018, issue 3, 3:18