COMBINED NUMERICAL AND EXPERIMENTAL INVESTIGATIONS OF FLOW OF COOLANT IN THE REACTOR CORE CASSETTE FIRST FLOATING POWER UNIT

Authors & Affiliations

Dmitirev S.M., Varentsov A.V., Doronkov D.V., Legchanov M.A., Polozkova E.N., Solntsev D.N., Sorokin V.D., Khrobostov A.E.
Nizhny Novgorod State Technical University n.a. R.E. Alekseev, Nizhny Novgorod, Russia

Dmitriev S.M. - Rector, Dr. Sci. (Tech.), Professor, Nizhny Novgorod State Technical University n.a. R.E. Alekseev. Contacts: 24, Minina st., Nizhny Novgorod, Russia, 603950. Tel.: (831) 436-93-24; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it.
Khrobostov A.E. – Director of INI and T, Cand. Sci. (Tech.), Assistant Professor, Nizhny Novgorod State Technical University n.a. R.E. Alekseev.
Legchanov M.A. – Deputy director of INI and T, Cand. Sci. (Tech.), Assistant Professor, Nizhny Novgorod State Technical University n.a. R.E. Alekseev.
Solntsev D.N. – Assistant, Cand. Sci. (Tech.), Nizhny Novgorod State Technical University n.a. R.E. Alekseev.
Sorokin V.D. – Assistant, Nizhny Novgorod State Technical University n.a. R.E. Alekseev.
Varentsov A.V. – PhD student, Nizhny Novgorod State Technical University n.a. R.E. Alekseev.
Doronkov D.V. – PhD student, Nizhny Novgorod State Technical University n.a. R.E. Alekseev.
Polozkova E.N. – Master Student, Nizhny Novgorod State Technical University n.a. R.E. Alekseev.

Abstract

The results of experimental investigations of local hydrodynamics and intercell mass transfer of coolant flow in characteristic zones FA KLT-40C reactor unit behind a plate spacer grid have been presented. The investigations were carried out on an aerodynamic rig using the admixture diffusion method (the tracer-gas method). Study of spatial dispersion of absolute flow velocity projections and distribution of tracer concentration allowed to specify coolant flow picture behind the plate spacer grid FA of KLT-40C reactor unit. In this article the measurement results of liquid resistance of plate spacer grid in dependence to Reynolds number. On the base of received experimental data specification of procedure coolant load calculation recommendations for detailed cell-wise calculations of a core KLT-40C reactor unit have been written. Investigation results of local hydrodynamics and coolant flow mass transfer in FA KLT-40C reactor unit have been taken for practical use by Afrikantov OKBM JSC when assessing heat engineering reliability of cores KLT-40C reactor unit and are included in database for verification of CFD programs (CFD-codes) and detailed cell-wise calculation of reactor core KLT-40C.

Keywords
floating power unit, core, fuel assemblies, spacer grid, coolant flow hydrodynamics, coolant flow mass transfer, flow friction coefficients

Article Text (PDF, in Russian)

References

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UDC 621.039

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants", 2016, issue 3, 3:7

BROND-3.1

ISSUES

COMBINED NUMERICAL AND EXPERIMENTAL INVESTIGATIONS OF FLOW OF COOLANT IN THE REACTOR CORE CASSETTE FIRST FLOATING POWER UNIT