About: Fluid mixing and flow distribution in a primary circuit of a nuclear pressurized water reactor

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About: Fluid mixing and flow distribution in a primary circuit of a nuclear pressurized water reactor - Validation of CFD codes Goto Sponge NotDistinct Permalink

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rdf:type	skos:Concept http://linked.opendata.cz/ontology/domain/vavai/Vysledek
Description	The EU project FLOMIX-R was aimed at describing the mixing phenomena relevant for both safety analysis, particularly in steam line break and boron dilution scenarios, and mixing phenomena of interest for economical operation and the structural integrity.This report focuses on the computational fluid dynamics (CFD) code validation. CFD calculations have been accomplished for selected experiments with two different CFD codes (CFX, FLUENT). The matrix of benchmark cases contains slug mixing tests simulating the start-up of the first main circulation pump which have been performed with three 1:5 scaled facilities: the Rossendorf coolant mixing model ROCOM, the Vattenfall test facility and a metal mock-up of a VVER-1000 type reactor. The results of the CFD calculations are mostly in-between the uncertainty bands of the experiments. It can be concluded about the suitability of applying CFD methods in engineering applications for turbulent mixing in nuclear reactors. The EU project FLOMIX-R was aimed at describing the mixing phenomena relevant for both safety analysis, particularly in steam line break and boron dilution scenarios, and mixing phenomena of interest for economical operation and the structural integrity.This report focuses on the computational fluid dynamics (CFD) code validation. CFD calculations have been accomplished for selected experiments with two different CFD codes (CFX, FLUENT). The matrix of benchmark cases contains slug mixing tests simulating the start-up of the first main circulation pump which have been performed with three 1:5 scaled facilities: the Rossendorf coolant mixing model ROCOM, the Vattenfall test facility and a metal mock-up of a VVER-1000 type reactor. The results of the CFD calculations are mostly in-between the uncertainty bands of the experiments. It can be concluded about the suitability of applying CFD methods in engineering applications for turbulent mixing in nuclear reactors. (en)
Title	Fluid mixing and flow distribution in a primary circuit of a nuclear pressurized water reactor - Validation of CFD codes Fluid mixing and flow distribution in a primary circuit of a nuclear pressurized water reactor - Validation of CFD codes (en)
skos:prefLabel	Fluid mixing and flow distribution in a primary circuit of a nuclear pressurized water reactor - Validation of CFD codes Fluid mixing and flow distribution in a primary circuit of a nuclear pressurized water reactor - Validation of CFD codes (en)
skos:notation	RIV/46356088:_____/07:#0000961!RIV11-MPO-46356088
http://linked.open...avai/riv/aktivita	P
http://linked.open...avai/riv/aktivity	P(FT-TA3/071)
http://linked.open...iv/cisloPeriodika	237
http://linked.open...vai/riv/dodaniDat	2011
http://linked.open...aciTvurceVysledku	Vyskočil, Ladislav
http://linked.open.../riv/druhVysledku	J - Článek v odborném periodiku
http://linked.open...iv/duvernostUdaju	S - Úplné a pravdivé údaje nepodléhající ochraně podle zvláštních právních předpisů
http://linked.open...titaPredkladatele	ÚJV Řež, a. s.
http://linked.open...dnocenehoVysledku	422247
http://linked.open...ai/riv/idVysledku	RIV/46356088:_____/07:#0000961
http://linked.open...riv/jazykVysledku	eng - angličtina
http://linked.open.../riv/klicovaSlova	computational fluid dynamics; nuclear reactor; downcomer; mixing; validation (en)
http://linked.open.../riv/klicoveSlovo	nuclear reactor mixing computational fluid dynamics validation downcomer
http://linked.open...odStatuVydavatele	US - Spojené státy americké
http://linked.open...ontrolniKodProRIV	[9FB8BB602A4F]
http://linked.open...i/riv/nazevZdroje	Nuclear Engineering and Design
http://linked.open...in/vavai/riv/obor	JB
http://linked.open...ichTvurcuVysledku	1 (xsd:int)
http://linked.open...cetTvurcuVysledku	14 (xsd:int)
http://linked.open...vavai/riv/projekt	Safety aspects of advanced nuclear reactors.
http://linked.open...UplatneniVysledku	2007
http://linked.open...v/svazekPeriodika	2007
http://linked.open...iv/tvurceVysledku	Vyskočil, Ladislav
http://linked.open...ain/vavai/riv/wos	000249157000008
issn	0029-5493
number of pages	17 (xsd:int)

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