[en] The results of experimental researches of local hydrodynamic characteristics of the coolant flow in the fuel assemblies PWR reactors using different mixing grids are presented in the paper
[ru]
В работе приведены результаты экспериментальных исследований локальных гидродинамических характеристик потока теплоносителя в тепловыделяющих сборках реакторов PWR при использовании различных перемешивающих дистанционирующих решетокJournal
Izvestiya Vysshikh Uchebnykh Zavedenij. Yadernaya Ehnergetika; ISSN 0204-3327; 
; (no.3); p. 63-72
; (no.3); p. 63-72
[en] Results of experimental investigations of the local hydrodynamic and mass-exchange characteristics of a coolant flowing through the cells in the characteristic zones of a fuel assembly of a KLT- 40S reactor plant downstream of a plate-type spacer grid by the method of diffusion of a gas tracer in the coolant flow with measurement of its velocity by a five-channel pneumometric probe are presented. An analysis of the concentration distribution of the tracer in the coolant flow downstream of a plate-type spacer grid in the fuel assembly of the KLT-40S reactor plant and its velocity field made it possible to obtain a detailed pattern of this flow and to determine its main mechanisms and features. Results of measurement of the hydraulic-resistance coefficient of a plate-type spacer grid depending on the Reynolds number are presented. On the basis of the experimental data obtained recommendations for improvement of the method of calculating the flow rate of a coolant in the cells of the fissile core of a KLT-40S reactor were developed. The results of investigations of the local hydrodynamic and mass-exchange characteristics of the coolant flow in the fuel assembly of the KLT-40S reactor plant were accepted for estimating the thermal and technical reliability of the fissile cores of KLT-40S reactors and were included in the database for verification of computational hydrodynamics programs (CFD codes).(authors)
Journal
Inzhenerno-Fizicheskij Zhurnal; ISSN 0021-0285; ; v. 90(4); p. 988-996
; v. 90(4); p. 988-996
No abstract available
Source
Trufanov, A.A.; Sorokin, A.P. (eds.); Predpriyatie Goskorporatsii Rosatom AO Gosudarstvennyj Nauchnyj Tsentr Rossijskoj Federatsii - Fiziko-Ehnergeticheskij Inst. imeni A.I. Lejpunskogo, Obninsk (Russian Federation); 274 p; ISBN 978-5-906512-70-3; ; 2015; p. 62-63; Thermal physics of new generation reactors (Thermal physics-2015); Teplofizika reaktorov novogo pokoleniya (Teplofizika-2015); Obninsk (Russian Federation); 6-9 Oct 2015
; 2015; p. 62-63; Thermal physics of new generation reactors (Thermal physics-2015); Teplofizika reaktorov novogo pokoleniya (Teplofizika-2015); Obninsk (Russian Federation); 6-9 Oct 2015
[en] This paper presents the results of experimental investigations of the influence of mixing spacer grids with different types of deflectors on the coolant flow in the TVS-Kvadrat fuel assembly of the PWR-type reactor. Investigations were conducted on an aerodynamic stand with the use of a multichannel pneumometric probe. Analysis of the spatial distribution of projections of the absolute flow velocity permitted detailing the coolant flow pattern behind the mixing spacer grid with various types of deflectors of mixing grids. The results obtained in the present paper are used to verify three-dimensional CFD programs, and in applied cell by cell codes they also serve as a database in calculations of thermotechnical reliability of the cores of PWR-type reactors with the TVS-Kvadrat. (authors)
Journal
Inzhenerno-Fizicheskij Zhurnal; ISSN 0021-0285; ; v. 90(5); p. 1193-1199
; v. 90(5); p. 1193-1199