Computational and Experimental Investigations of the Coolant Flow in the Cassette Fissile Core of a KLT-40S Reactor

被引：9

作者：

Dmitriev S.M. ^{[1
]}

Varentsov A.V. ^{[1
]}

Dobrov A.A. ^{[1
]}

Doronkov D.V. ^{[1
]}

Pronin A.N. ^{[1
]}

Sorokin V.D. ^{[1
]}

Khrobostov A.E. ^{[1
]}

机构：

[1] R. E. Alekseev Nizhnii Novgorod State Technical University, 24 Minin Str., Nizhnii Novgorod

来源：

Journal of Engineering Physics and Thermophysics | 2017年 / 90卷 / 4期

关键词：

coolant; fissile core; floating power plant; fuel assembly; spacer grid;

D O I：

10.1007/s10891-017-1641-7

中图分类号：

学科分类号：

摘要：

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). © 2017, Springer Science+Business Media, LLC.

引用

页码：941 / 950

页数：9

共 9 条

[1] Dmitriev S.M., Zverev D.L., Bykh O.A., Panov Y.K., Farafonov V.A., Main Equipment of an Atomic Power Plant [in Russian], (2015)
[2] Dmitriev S.M., Bykh O.A., Panov Y.K., Sorokin N.M., Zverev D.L., Farafonov V.A., Main Equipment of an Atomic Power Plant with Shell-Type Thermal Reactors [in Russian], (2013)
[3] Dmitriev S.M., Barinov A.A., Borodina V.E., Khrobostov A.E., On the methodology of substantiation of the thermal and technical reliability of the fissile cores of water-moderated power reactors, Tr. Nizhegorodsk. Gos. Tekh. Univ. im. R. E. Alekseeva, 2, pp. 98-108, (2014)
[4] Dmitriev S.M., Dobrov A.A., Legchanov M.A., Khrobostov A.E., Use of a multichannel pneumometric probe in investigating the profile of the coolant-flow velocity in model fuel assemblies of nuclear reactors, Prib. Metody Izmer., 6, 2, pp. 188-195, (2015)
[5] Dmitriev S.M., Borodin S.S., Legchanov M.A., Solntsev D.N., Sorokin V.D., Khrobostov A.E., Experimental investigations of the hydrodynamic and mass-exchange characteristics of the coolant flow in the fuel assembly of a VVER reactor, At. Énerg., 113, 5, pp. 252-257, (2012)
[6] Dmitriev S.M., Varentsov A.V., Dobrov A.A., Doronkov D.V., Samoilov O.B., Sorokin V.D., Khrobostov A.E., Calculation and experimental investigations of the local hydrodynamic and mass-exchange characteristics of the coolant flow in the fuel-assembly quadrate of PWR reactors with mixing grids, Teploénergetika, 8, pp. 20-27, (2014)
[7] Zhukov A.V., Matyukhin N.M., Sorokin A.P., Interchannel exchange in the fuel assemblies of fast reactors, in: Theoretical Bases and Physics of a Process [in Russian], (1989)
[8] Dmitriev S.M., Borodin S.S., Varentsov A.V., Legchanov M.A., Sorokin V.D., Khrobostov A.E., Experimental investigations of the local hydrodynamics of the coolant flow in the fuel assembly of a PWR reactor supplied with mixing spacer grids including deflectors of different types, Izv. Vyssh. Uchebn. Zaved., Yad. Énerg., 3, pp. 63-72, (2015)
[9] Program "KANAL," Description of Application [in Russian], OKBM, Nizhnii Novgorod, (2013)

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