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Statements

Subject Item
n2:RIV%2F46356088%3A_____%2F08%3A%230001219%21RIV13-MPO-46356088
rdf:type
skos:Concept n16:Vysledek
dcterms:description
This paper presents a CFD simulation of selected “Large Water Loop” critical heat flux experiments. Calculations were performed by NEPTUNE_CFD code. The Large Water Loop (LWL) is non-active pressurised-water equipment with technological and thermal parameters corresponding to those of PWR. Thirteen CHF tests were calculated with NEPTUNE. In all calculated tests, a sudden rise of the wall temperature was observed. Simulations of cases with a higher mass flux were successful. Simulation of cases with a low mass flux indicates that the modelling approach might not be suitable for lower mass fluxes. The results show that NEPTUNE has some potential for predicting boiling flow up to CHF in the reactor fuel assembly. Proceedings of XCFD4NRS, Experiments and CFD Code Applications to Nuclear Reactor Safety OECD/NEA & IAEA, Grenoble, France, 10 - 12 September 2008. This paper presents a CFD simulation of selected “Large Water Loop” critical heat flux experiments. Calculations were performed by NEPTUNE_CFD code. The Large Water Loop (LWL) is non-active pressurised-water equipment with technological and thermal parameters corresponding to those of PWR. Thirteen CHF tests were calculated with NEPTUNE. In all calculated tests, a sudden rise of the wall temperature was observed. Simulations of cases with a higher mass flux were successful. Simulation of cases with a low mass flux indicates that the modelling approach might not be suitable for lower mass fluxes. The results show that NEPTUNE has some potential for predicting boiling flow up to CHF in the reactor fuel assembly. Proceedings of XCFD4NRS, Experiments and CFD Code Applications to Nuclear Reactor Safety OECD/NEA & IAEA, Grenoble, France, 10 - 12 September 2008.
dcterms:title
Simulation of Critical Heat Flux Experiments in NEPTUNE_CFD Code Simulation of Critical Heat Flux Experiments in NEPTUNE_CFD Code
skos:prefLabel
Simulation of Critical Heat Flux Experiments in NEPTUNE_CFD Code Simulation of Critical Heat Flux Experiments in NEPTUNE_CFD Code
skos:notation
RIV/46356088:_____/08:#0001219!RIV13-MPO-46356088
n3:aktivita
n6:P
n3:aktivity
P(FT-TA4/083)
n3:dodaniDat
n10:2013
n3:domaciTvurceVysledku
n13:7450060 n13:2435462
n3:druhVysledku
n4:O
n3:duvernostUdaju
n14:S
n3:entitaPredkladatele
n8:predkladatel
n3:idSjednocenehoVysledku
394861
n3:idVysledku
RIV/46356088:_____/08:#0001219
n3:jazykVysledku
n15:eng
n3:klicovaSlova
computational fluid dynamics; subcooled boiling; critical heat flux; wall-heat-flux; splitting; interfacial area transport
n3:klicoveSlovo
n11:splitting n11:computational%20fluid%20dynamics n11:critical%20heat%20flux n11:subcooled%20boiling n11:wall-heat-flux n11:interfacial%20area%20transport
n3:kontrolniKodProRIV
[F59675E262DE]
n3:obor
n12:JB
n3:pocetDomacichTvurcuVysledku
2
n3:pocetTvurcuVysledku
2
n3:projekt
n9:FT-TA4%2F083
n3:rokUplatneniVysledku
n10:2008
n3:tvurceVysledku
Macek, Jiří Vyskočil, Ladislav