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

Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21220%2F19%3A00338806" target="_blank" >RIV/68407700:21220/19:00338806 - isvavai.cz</a>
Result on the web
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DOI - Digital Object Identifier
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Result language
angličtina
Original language name
SIMULATION OF CROSSFLOWS IN A MIXED CORE OF VVER REACTOR WITH SUBCHANNEL CODE AND CFD CODE
Original language description
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.
Czech name
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Czech description
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Project
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Continuities
I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Publication year
2019
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

Article name in the collection
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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Number of pages
13
Pages from-to
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Publisher name
Atomic Energy Research
Place of publication
Budapest
Event location
Mochovce
Event date
Oct 14, 2019
Type of event by nationality
WRD - Celosvětová akce
UT code for WoS article
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