SIMULATION OF CROSSFLOWS IN A MIXED CORE OF VVER REACTOR WITH SUBCHANNEL CODE AND CFD CODE

Kód výsledku v IS VaVaI

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Výsledek na webu

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DOI - Digital Object Identifier

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Jazyk výsledku

angličtina

Název v původním jazyce

SIMULATION OF CROSSFLOWS IN A MIXED CORE OF VVER REACTOR WITH SUBCHANNEL CODE AND CFD CODE

Popis výsledku v původním jazyce

The goal of this work was to evaluate crossflows in a mixed core of VVER reactor. The mixed core consists of old and new fuel assemblies with different geometry. These fuel assemblies have different spacer grids and mixing grids at different elevations. The old and new fuel assemblies also have slightly different total pressure loss. This causes crossflows between neighboring fuel assemblies. Crossflows were evaluated with VIPRE-01 subchannel code and with Ansys Fluent CFD code. In both codes, the computational domain covers an interface among fuel assemblies of different type along the whole core height. VIPRE-01 domain is modeled pin-by-pin and it includes corner plates. Spacer and mixing grids are represented by local pressure losses. CFD model has a much finer grid resolution. Spacer and mixing grids are modeled by thin walls and porous zones. Due to the enormous size and complexity of the CFD domain, the mixing vanes were not modeled. Transverse coolant velocities along the core height were calculated in both codes and compared. The results obtained with subchannel code are in a quite good agreement with results from CFD simulation.

Název v anglickém jazyce

SIMULATION OF CROSSFLOWS IN A MIXED CORE OF VVER REACTOR WITH SUBCHANNEL CODE AND CFD CODE

Popis výsledku anglicky

The goal of this work was to evaluate crossflows in a mixed core of VVER reactor. The mixed core consists of old and new fuel assemblies with different geometry. These fuel assemblies have different spacer grids and mixing grids at different elevations. The old and new fuel assemblies also have slightly different total pressure loss. This causes crossflows between neighboring fuel assemblies. Crossflows were evaluated with VIPRE-01 subchannel code and with Ansys Fluent CFD code. In both codes, the computational domain covers an interface among fuel assemblies of different type along the whole core height. VIPRE-01 domain is modeled pin-by-pin and it includes corner plates. Spacer and mixing grids are represented by local pressure losses. CFD model has a much finer grid resolution. Spacer and mixing grids are modeled by thin walls and porous zones. Due to the enormous size and complexity of the CFD domain, the mixing vanes were not modeled. Transverse coolant velocities along the core height were calculated in both codes and compared. The results obtained with subchannel code are in a quite good agreement with results from CFD simulation.

Druh

D - Stať ve sborníku

CEP obor

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OECD FORD obor

20303 - Thermodynamics

Projekt

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Návaznosti

I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Rok uplatnění

2019

Kód důvěrnosti údajů

S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

Název statě ve sborníku

Proceedings of the 29th Symposium of AER on VVER Reactor Physics and Reactor Safety

ISBN

978-963-7351-32-7

ISSN

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e-ISSN

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Počet stran výsledku

13

Strana od-do

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Název nakladatele

Atomic Energy Research

Místo vydání

Budapest

Místo konání akce

Mochovce

Datum konání akce

14. 10. 2019

Typ akce podle státní příslušnosti

WRD - Celosvětová akce

Kód UT WoS článku

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