PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY
Series: Nuclear and Reactor Constants

since 1971

Русский (РФ)

ISSN 2414-1038 (online)

Authors & Affiliations

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

Dmitriev S.M. – Rector, Dr. Sci.(Tech.), Institute of Nuclear Power Engineering and Technical Physics, Nizhny Novgorod State Technical University. R.E. Alekseeva.
Barinov A.A. – postgraduate student, 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..
Solntsev D.N. – Associate Professor, Cand. Sci. (Tech.), Institute of Nuclear Power Engineering and Technical Physics, Nizhny Novgorod State Technical University. R.E. Alekseeva.
Sorokin V.D. – Engeneer, Institute of Nuclear Power Engineering and Technical Physics, Nizhny Novgorod State Technical University. R.E. Alekseeva.

Abstract

Currently actively developed software products in Russia and abroad, which allow describing the mixing processes of turbulent flows in the main equipment of nuclear power units, need verification. In this connection, this research is devoted to experimental studies of mixing processes in a pressurized water reactor model. The goal of this research is creation of benchmarks for the verification of Russian programs of computational fluid dynamics creating benchmarks for the verification of domestic codes of computational fluid dynamics. The experimental part of the study was carried out on a large-scale facility FT-40 of the laboratory "Reactor hydrodynamics" which is based in the NSTU R.E. Alekseeva. At this stage, experimental studies were conducted at a single coolant temperature. Sodium sulfate was used as a tracer. In this paper, a spatial conductometric measuring system is presented. This system allows investigating the flow mixing in equipment with complex geometry. The paper presents a description of the experimental regimes carried out, including a matrix of the regime parameters at which the studies were performed, as well as the results obtained. Conclusions are drawn about the prospects of using spatial conductometry as an inverse-resolution measuring method. Continuation of work in this direction will allow accumulating the necessary amount of highprecision experimental data for verification of Russian codes of computational hydrodynamics.

Keywords
nuclear reactor, mixing processes, coolant, spatial conductometry, computational fluid dynamics, CFD code

Article Text (PDF, in Russian)

References

UDC 621.029

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2018, issue 3, 3:11