Investigating hydrodynamic characteristics and peculiarities of the coolant flow behind a spacer grid of a fuel rod assembly of the floating nuclear power unit
S.M. Dmitriev, D.V. Doronkov, M.A. Legchanov, A.N. Pronin, D.N. Solncev, V.D. Sorokin, and A.E. Hrobostov
Nizhny Novgorod State Technical University named after R.E. Alekseev, Nizhny Novgorod, Russia
E-mail: nevid000@mail.ru
Keywords: core, fuel rod assembly (FA), spacer grid, flow friction coefficient, hydrodynamics of coolant
Pages: 369–378
Abstract
The results of
experimental investigations of local hydrodynamics of a coolant flow in fuel
rod assembly (FA) of KLT-40C
reactor behind a plate spacer grid have been presented. The investigations were
carried out on an aero-dynamic rig using the gas-phase diffusive tracer test.
An analysis of spatial distribution of absolute flow velocity projections and
distribution of tracer concentration allowed specifying a coolant flow pattern
behind the plate spacer grid of the FA. On the basis of obtained experimental
data the recommendations were provided to specify procedures for determining
the coolant flow rates for the programs of cell-wise calculation of a core zone
of KLT-40C
reactor. Investigation results were accepted for the practical use in JSC “OKBM
Afrikantov” to assess heat engineering reliability
of cores of KLT-40C
reactor and were included in a database for verification of CFD programs
(CFD-codes).
DOI: 10.1134/S0869864316030069
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