MyrrhaFoam: A CFD model for the study of the thermal hydraulic behavior of MYRRHA

Koloszar, Lilla; Buckingham, Sophia; Planquart, Philippe; Keijers, S.

doi:10.1016/j.nucengdes.2016.05.008

Cited by 16 publications

(5 citation statements)

References 5 publications

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“…Then properties of porous media are determined by two physical quantities, that is, porosity and permeability. The real porosity of the LBE reactor core is 0.2-0.4 (Koloszar et al, 2015). In this model, the porosity of the core is 0.3 and the porosity of the HX is 0.62 (Koloszar et al, 2014).…”

Section: Fluid Flow Modelmentioning

confidence: 99%

Multi-Physics Model Development for Polonium Transport Behavior in a Lead-Cooled Fast Reactor

et al. 2021

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210Po, a highly toxic element with strong volatility, is one of the main source terms of a Gen-IV lead-cooled fast reactor (LFR). Therefore, the radioactive safety caused by 210Po has become an important topic in LFR-related research. In order to simulate the behavior of 210Po in an LFR, this work developed a multi-physics model of an LFR from the perspective of radioactive transport. Considering the effects of nuclide decay, cover gas leakage, containment ventilation, and Po aerosol deposition, a comprehensive simulation was carried out to evaluate the sensitivity of those effects on the 210Po distribution in detail. Preliminary results indicate that during normal operation, most of the 210Po in the LBE exist in the form of PbPo, and around 10–9 of 210Po could evaporate from the LBE into the cover gas, and then further leak into the containment. In addition, even if the leakage rate of 210Po in the cover gas into the containment is maintained at 5‰ per day, due to the deposition of Po aerosol, the 210Po contamination on the inner surface of the containment is still below the radioactivity concentration limits.

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Section: Fluid Flow Modelmentioning

confidence: 99%

Multi-Physics Model Development for Polonium Transport Behavior in a Lead-Cooled Fast Reactor

et al. 2021

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“…And a reference case was utilized to provide a baseline model. According to the design of MYRRHA [10,11], the porosity of reactor core is set to 0.3 and the porosity of HX is set to 0.62 in this baseline model, where permeability means the resistance of fluid flowing through porous medium in three dimensions. And a lower permeability means a stronger resistance.…”

Section: Operation Condition Of Typical Lfrmentioning

confidence: 99%

Prediction of Global Corrosion and Corrosion Products Behavior in the Primary Circuit of LBE Fast Reactor

Wu¹,

Wu²,

Wang³

et al. 2021

Preprint

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For better understanding the corrosion and corrosion products behavior in the primary circuit of lead-bismuth eutectic (LBE) coolant reactor, the concentration distribution of soluble impurities and the transport of solid particles are investigated through finite-element method. An axisymmetric model of the primary circuit of LBE reactor was constructed to accelerate the calculation the thermal hydraulic filed of circuit. The saturation concentration of solute Fe, Cr and Ni in LBE coolant are identified through the equilibrium of their oxides and PbO. And the very different saturation concentrations of Fe/Cr/Ni in LBE will lead to significant element selective corrosion. The migration of solid oxides particles in the primary circuit is also investigated by the Euler-Lagrange tracing model. The simulation shows that driving force for the movement of particles &gt;100 μm is buoyancy, which lets particles float on a free surface, while particles &lt;10 μm tend to suspend in coolant. However, the behavior of particles also depends on the formation position, the particles formed above the core have the high possibility of re-entering in the core.

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“…The mainstream conceptual design in the world and their principal parameters are listed in Table 1. A reference case was utilized as baseline model, the porosity of the reactor core is calculated as 0.3 and the porosity of HX is 0.62 according to the design of MYRRHA [19,20]. Permeability means the resistance of fluid flowing through porous medium in three dimensions.…”

Section: Service Condition Of Structure Materials In Lfr 21 Operation Condition Of Typical Lfrmentioning

confidence: 99%

Prediction of Dissolved Impurities and Movement of Oxide Particles in the Primary Circuit of LBE Fast Reactor

Wu¹,

Wang³

et al. 2021

Coatings

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To better understand the corrosion and corrosion products behavior in the primary circuit of lead-bismuth eutectic (LBE) coolant reactor, the concentration distribution of soluble impurities and the transport of solid particles are investigated through the finite-element method. An axisymmetric model of the primary circuit of an LBE reactor was constructed to accelerate the calculation of the thermal hydraulic filed of the circuit. The saturation concentration of solute Fe, Cr and Ni in LBE coolant are identified through the equilibrium of their oxides and PbO, and the very different saturation concentrations of Fe/Cr/Ni in LBE will lead to significant element-selective corrosion. The migration of solid oxide particles in the primary circuit is also investigated by the Euler–Lagrange tracing model. The simulation shows that driving force for the movement of particles >100 μm is buoyancy, which lets particles float on a free surface, while particles <10 μm tend to suspend in coolant. However, the behavior of particles also depends on the formation position, the particles formed above the core have a high possibility of re-entering in the core.

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MyrrhaFoam: A CFD model for the study of the thermal hydraulic behavior of MYRRHA

Cited by 16 publications

References 5 publications

Multi-Physics Model Development for Polonium Transport Behavior in a Lead-Cooled Fast Reactor

Multi-Physics Model Development for Polonium Transport Behavior in a Lead-Cooled Fast Reactor

Prediction of Global Corrosion and Corrosion Products Behavior in the Primary Circuit of LBE Fast Reactor

Prediction of Dissolved Impurities and Movement of Oxide Particles in the Primary Circuit of LBE Fast Reactor

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