LATERAL COOLANT FLOW BETWEEN FUEL ASSEMBLIES IN MIXED CORES

This paper presents the results of an analysis of lateral coolant flow between adjacent fuel assemblies with non-identical spacing grids in a mixed core consisting of TVSA-T mod.1 and TVSA-T mod.2 fuel assemblies. The calculation was carried out using modified subchannel code SUBCAL which allows to...

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Main Authors: Vojtech Caha, Jiří Čížek
Format: Article
Language:English
Published: CTU Central Library 2018-05-01
Series:Acta Polytechnica CTU Proceedings
Subjects:
Online Access:https://ojs.cvut.cz/ojs/index.php/APP/article/view/4836
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spelling doaj-8a9f0ab93dd04bdb89cfa226b4d546792020-11-24T23:21:32ZengCTU Central LibraryActa Polytechnica CTU Proceedings2336-53822018-05-011401710.14311/APP.2018.14.00014104LATERAL COOLANT FLOW BETWEEN FUEL ASSEMBLIES IN MIXED CORESVojtech Caha0Jiří Čížek1Department of Nuclear Reactors, FNSPE, CTU in Prague, V Holešovickách 2, Prague, Czech Republic Chemcomex, a.s., Elišky Premyslovny 379, Prague, Czech RepublicChemcomex, a.s., Elišky Premyslovny 379, Prague, Czech RepublicThis paper presents the results of an analysis of lateral coolant flow between adjacent fuel assemblies with non-identical spacing grids in a mixed core consisting of TVSA-T mod.1 and TVSA-T mod.2 fuel assemblies. The calculation was carried out using modified subchannel code SUBCAL which allows to calculate 3D thermo-hydraulic characteristics of the coolant flow in the full three fuel assemblies model. This full three fuel assemblies model was created in two variants. The first variant consisted of three hydraulically identical fuel assemblies TVSA-T mod.1, whereas the second variant consisted of two fuel assemblies TVSA-T mod.1 and one fuel assembly TVSA-T mod.2 which mainly differ in types, number and axial coordinate of spacing grids and also in diameter of guide tubes. The influence of mixed core to lateral coolant flow and hence coolant temperature was obtained by comparing these two variants. The power distribution was taken from presumed mixed core fuel reload calculated by macro-code ANDREA. Finally there were also provided a comparison of results achieved by subchannel analysis approach with calculation of similar problem using CFD code ANSYS CFX by TVEL, the fuel supplier.https://ojs.cvut.cz/ojs/index.php/APP/article/view/4836subchannel analysis, SUBCAL, mixed core, thermal-hydraulics
collection DOAJ
language English
format Article
sources DOAJ
author Vojtech Caha
Jiří Čížek
spellingShingle Vojtech Caha
Jiří Čížek
LATERAL COOLANT FLOW BETWEEN FUEL ASSEMBLIES IN MIXED CORES
Acta Polytechnica CTU Proceedings
subchannel analysis, SUBCAL, mixed core, thermal-hydraulics
author_facet Vojtech Caha
Jiří Čížek
author_sort Vojtech Caha
title LATERAL COOLANT FLOW BETWEEN FUEL ASSEMBLIES IN MIXED CORES
title_short LATERAL COOLANT FLOW BETWEEN FUEL ASSEMBLIES IN MIXED CORES
title_full LATERAL COOLANT FLOW BETWEEN FUEL ASSEMBLIES IN MIXED CORES
title_fullStr LATERAL COOLANT FLOW BETWEEN FUEL ASSEMBLIES IN MIXED CORES
title_full_unstemmed LATERAL COOLANT FLOW BETWEEN FUEL ASSEMBLIES IN MIXED CORES
title_sort lateral coolant flow between fuel assemblies in mixed cores
publisher CTU Central Library
series Acta Polytechnica CTU Proceedings
issn 2336-5382
publishDate 2018-05-01
description This paper presents the results of an analysis of lateral coolant flow between adjacent fuel assemblies with non-identical spacing grids in a mixed core consisting of TVSA-T mod.1 and TVSA-T mod.2 fuel assemblies. The calculation was carried out using modified subchannel code SUBCAL which allows to calculate 3D thermo-hydraulic characteristics of the coolant flow in the full three fuel assemblies model. This full three fuel assemblies model was created in two variants. The first variant consisted of three hydraulically identical fuel assemblies TVSA-T mod.1, whereas the second variant consisted of two fuel assemblies TVSA-T mod.1 and one fuel assembly TVSA-T mod.2 which mainly differ in types, number and axial coordinate of spacing grids and also in diameter of guide tubes. The influence of mixed core to lateral coolant flow and hence coolant temperature was obtained by comparing these two variants. The power distribution was taken from presumed mixed core fuel reload calculated by macro-code ANDREA. Finally there were also provided a comparison of results achieved by subchannel analysis approach with calculation of similar problem using CFD code ANSYS CFX by TVEL, the fuel supplier.
topic subchannel analysis, SUBCAL, mixed core, thermal-hydraulics
url https://ojs.cvut.cz/ojs/index.php/APP/article/view/4836
work_keys_str_mv AT vojtechcaha lateralcoolantflowbetweenfuelassembliesinmixedcores
AT jiricizek lateralcoolantflowbetweenfuelassembliesinmixedcores
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