Validation of the CFX4 CFD code for containment thermal-hydraulics

Houkema, M.; Siccama, N.B.; Nijeholt, J.A. Lycklama à; Komen, E.M.J.

doi:10.1016/j.nucengdes.2007.02.033

Cited by 56 publications

(9 citation statements)

References 4 publications

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“…Karkoszka and Anglart [150] gave the multidimensional model of convection condensation for binary and ternary mixtures of vapor and NCG forced by gravity, while Houkema et al [151] used the commercial computational fluid dynamics code CFX4 to model the turbulent film condensation heat transfer process.…”

Section: Mathematical Modelmentioning

confidence: 99%

“…After that, Zschaeck [152] developed Houkema's [151] model of turbulent film condensation heat transfer process, they assumed that the condensation rate was controlled by the concentration boundary layer, the partial pressure of the condensable component at the wall was equal to its saturation pressure evaluated at the interface temperature, wall functions were not influenced by wall suction. They considered the features of NCG accumulation, coupled cooling water heat transfer, and simulated the condenser tube inside and outside (in particular, the mass fraction distribution of the vapor caused by NCG accumulation near the liquidegas interface).…”

Section: Mathematical Modelmentioning

confidence: 99%

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Review of vapor condensation heat and mass transfer in the presence of non-condensable gas

Huang

Zhang

Wang

2015

Applied Thermal Engineering

207

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Section: Mathematical Modelmentioning

confidence: 99%

Section: Mathematical Modelmentioning

confidence: 99%

Review of vapor condensation heat and mass transfer in the presence of non-condensable gas

Huang

Zhang

Wang

2015

Applied Thermal Engineering

207

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“…The effect of this water condensate on for instance the flow, heat transfer and condensation is thus neglected. The NRG condensation model is described in more detail by Houkema et al (2008) and has been employed successfully in the SARNET Condensation Benchmark (Ambrosini et al, 2007) and International Standard Problem ISP-47 on Containment Thermalhydraulics (Allelein et al, 2007).…”

Section: Nrg Condensation Modelmentioning

confidence: 99%

Validation of a FLUENT CFD model for hydrogen distribution in a containment

Visser

Houkema

Siccama

et al. 2012

Nuclear Engineering and Design

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a b s t r a c tHydrogen may be released into the containment atmosphere of a nuclear power plant during a severe accident. Locally, high hydrogen concentrations may be reached that can possibly cause fast deflagration or even detonation and put the integrity of the containment at risk. The distribution and mixing of hydrogen is, therefore, an important safety issue for nuclear power plants.Computational fluid dynamics (CFD) codes can be applied to predict the hydrogen distribution in the containment within the course of a hypothetical severe accident and get an estimate of the local hydrogen concentration in the various zones of the containment. In this way the risk associated with the hydrogen safety issue can be determined, and safety related measurements and procedures could be assessed. In order to further validate the CFD containment model of NRG in the context of hydrogen distribution in the containment of a nuclear power plant, the HM-2 test performed in the German THAI (thermalhydraulics, hydrogen, aerosols and iodine) facility is selected. In the first phase of the HM-2 test a stratified hydrogen-rich light gas layer was established in the upper part of the THAI containment. In the second phase steam was injected at a lower position. This induced a rising plume that gradually dissolved the stratified hydrogen-rich layer from below. Phenomena that are expected in severe accidents, like natural convection, turbulent mixing, condensation, heat transfer and distribution in different compartments, are simulated in this hypothetical severe accident scenario.The hydrogen distribution and associated physical phenomena monitored during the HM-2 test are predicted well by the CFD containment model. Sensitivity analyses demonstrated that a mesh resolution of 45 mm in the bulk and 15 mm near the walls is sufficiently small to adequately model the hydrogen distribution and dissolution processes in the THAI HM-2 test. These analyses also showed that wall functions could be applied. Sensitivity analyses on the effect of the turbulence model and turbulence settings revealed that it is important to take the effect of buoyancy on the turbulent kinetic energy into account. When this effect of buoyancy is included, the results of the standard k-ε turbulence model and SST k-ω turbulence model are similar and agree well with experiment. The outcome of these sensitivity analyses can be used as input for setting up the guidelines on the application of CFD for containment issues.

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“…The mass sink was calculated from (2) for each cell where the "bulk flow" physical quantities (temperature, steam density, and noncondensible gas density) were evaluated at the cell centre. As the temperature of the gaseous mixture corresponding to the cell centre appears in (2) and 3, the calculated condensation rate and enthalpy sink necessarily depend on the width of cells contiguous to the condensation surface (Kljenak et al, 2006 [4]). The saturation pressure at condensing wall temperature was calculated, and it was ensured that steam partial pressure must be higher than the saturation pressure at the temperature of the wall for condensation to occur.…”

Section: Mathematical Modelmentioning

confidence: 99%

Computational Fluid Dynamics Modeling of Steam Condensation on Nuclear Containment Wall Surfaces Based on Semiempirical Generalized Correlations

Sharma

Gera

Singh

et al. 2012

Science and Technology of Nuclear Installations

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In water-cooled nuclear power reactors, significant quantities of steam and hydrogen could be produced within the primary containment following the postulated design basis accidents (DBA) or beyond design basis accidents (BDBA). For accurate calculation of the temperature/pressure rise and hydrogen transport calculation in nuclear reactor containment due to such scenarios, wall condensation heat transfer coefficient (HTC) is used. In the present work, the adaptation of a commercial CFD code with the implementation of models for steam condensation on wall surfaces in presence of noncondensable gases is explained. Steam condensation has been modeled using the empirical average HTC, which was originally developed to be used for “lumped-parameter” (volume-averaged) modeling of steam condensation in the presence of noncondensable gases. The present paper suggests a generalized HTC based on curve fitting of most of the reported semiempirical condensation models, which are valid for specific wall conditions. The present methodology has been validated against limited reported experimental data from the COPAIN experimental facility. This is the first step towards the CFD-based generalized analysis procedure for condensation modeling applicable for containment wall surfaces that is being evolved further for specific wall surfaces within the multicompartment containment atmosphere.

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Validation of the CFX4 CFD code for containment thermal-hydraulics

Cited by 56 publications

References 4 publications

Review of vapor condensation heat and mass transfer in the presence of non-condensable gas

Review of vapor condensation heat and mass transfer in the presence of non-condensable gas

Validation of a FLUENT CFD model for hydrogen distribution in a containment

Computational Fluid Dynamics Modeling of Steam Condensation on Nuclear Containment Wall Surfaces Based on Semiempirical Generalized Correlations

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