Abstract
Cathare-3 is the new version of the French Thermal-hydraulic code for the safety analysis of nuclear reactors, its 3D module is mainly used to model the reactor vessel with a “porous” medium approach of two-fluid six equations model. Therefore, the balance equations are established using a double-averaged method: first, a time-average, and then, space-average. Optional terms can be added in momentum and energy balance equations to model turbulent diffusion and dispersion effects. These terms have an impact on core simulations at subchannel scale. So, the Cathare team have established models for these terms in rod bundle geometry and had validated them on various experiments. The presented simulations are a 3D modeling of the core of the ROSA-2/LSTF experiment using Cathare-3 3-D module with a radial nodalization of one mesh per rod. A phase of core uncovering during which the rod temperatures in the dry zone increase is observed in an experimental test and experimental evolutions of rods and gas temperatures are compared with Cathare-3 calculations with and without the turbulent terms.
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Notes
- 1.
GRAZIELLA and OMEGA-2 test sections do not include mixing vane on spacer grids. On heated tests, A constant of the turbulent diffusion and dispersion of energy model (Eq. 8) must be divided by a factor 30 to obtain the right temperature gradients.
- 2.
Of about 15 seconds on the instant of start of increase which is equivalent to 10 cm on the swell level - this is lower than the experimental uncertainty of the collapsed level.
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Préa, R., Mekkas, A. (2021). Rod-Bundle Thermalhydraulics Mixing Phenomena: 3D Analysis with Cathare-3 of ROSA-2/LSTF Experiment. In: Deville, M., et al. Turbulence and Interactions. TI 2018 2018. Notes on Numerical Fluid Mechanics and Multidisciplinary Design, vol 149. Springer, Cham. https://doi.org/10.1007/978-3-030-65820-5_17
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