2008
DOI: 10.1155/2008/434212
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CFD Code Validation against Stratified Air-Water Flow Experimental Data

Abstract: Pressurized thermal shock (PTS) modelling has been identified as one of the most important industrial needs related to nuclear reactor safety. A severe PTS scenario limiting the reactor pressure vessel (RPV) lifetime is the cold water emergency core cooling (ECC) injection into the cold leg during a loss of coolant accident (LOCA). Since it represents a big challenge for numerical simulations, this scenario was selected within the European Platform for Nuclear Reactor Simulations (NURESIM) Integrated Project a… Show more

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Cited by 14 publications
(7 citation statements)
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“…Therefore Holmås et al [10] concluded that the turbulence models had to be modified in order to correctly predict the turbulence at the gas-liquid interface. The same conclusion was drawn by Terzuoli et al [13], who used the commercial codes CFX 10.0 and Fluent 6.1 to simulate the experiment of air-water in a channel by Fabre et al [14]. The VOF method was employed, with the k-ω SST model for the turbulence.…”
Section: Introductionmentioning
confidence: 75%
“…Therefore Holmås et al [10] concluded that the turbulence models had to be modified in order to correctly predict the turbulence at the gas-liquid interface. The same conclusion was drawn by Terzuoli et al [13], who used the commercial codes CFX 10.0 and Fluent 6.1 to simulate the experiment of air-water in a channel by Fabre et al [14]. The VOF method was employed, with the k-ω SST model for the turbulence.…”
Section: Introductionmentioning
confidence: 75%
“…( 5). Terzuoli et al [39] defined the lift force acting on a secondary phase p in a primary phase q as:…”
Section: Simulation Approachmentioning
confidence: 99%
“…The mentioned code has been chosen because the CFX solver [24], which is part of ANSYS/CFX, has demonstrated satisfactory results during its verification by test simulations of the standard international problem ISP-47 and its analogs under an IAEA task order [2,13,25]. The second step is solving a model heat transfer problem, the sketch of which is shown in Figure 2.…”
Section: Accounting For the Effects Of The Containment's Steel Linermentioning
confidence: 99%
“…The paper describes an approach to fluid dynamics simulations of processes occurring inside the nuclear power plant (NPP) containment during operation of spray systems in severe accidents. This topic is relevant at the current stage of advancement in high-accuracy numerical simulations of NPP operation [1][2][3]. In the case of interest, accidental releases mostly occur as a result of a coolant leak or line rupture in the main coolant circuit of the reactor building.…”
Section: Introductionmentioning
confidence: 99%