Rod bundle thermalhydraulics mixing phenomena: 3D analysis with CATHARE 3 of various experiments, Proceedings of the 15th International Topical Meeting on Nuclear Reactor Thermal-hydraulics (NURETH15), 2013. ,
Analysis of subchannel and rod bundle PSBT experiments with CATHARE 3, 2012. ,
Subchannel and rod bundle PSBT simulations with CATHARE 3, 2011. ,
Improved PWR LOCA simulations through refined core 3D simulations-an advanced 3D modeling and associated METERO validation program, NUTHOS-12, 2018. ,
Investigation of combined free and forced convection in a 2 x 6 rod bundle. No. BNWL--2216, 1977. ,
Investigation of combined free and forced convection in a 2 x 6 rod bundle during controlled flow transients. No. PNL--3135, 1980. ,
Open duct cooling-concept for the radial blanket region of a fast breeder reactor, Nuclear Engineering and Design, vol.16, pp.375-386, 1971. ,
, OECD/NRC Benchmark Based on NUPEC PWR Sub-channel and Bundle Test (PSBT), Nuclear Science, 2012.
A macroscopic turbulence model for flow in porous media suited for channel, pipe and rod bundle flows, International journal of heat and mass transfer, vol.49, pp.2739-2750, 2006. ,
A new turbulence model for porous media flows. Part I: Constitutive equations and model closure, International Journal of Heat and Mass Transfer, vol.52, pp.4264-4272, 2009. ,
Analysis of PSBT benchmark exercises for void distribution and DNB using a subchannel code MATRA, 2011. ,
Assessing the accuracy of energy turbulent diffusion dispersion correlation in a porous two-fluid model dedicated to PWR core simulations, Milieux Poreux -JEMP, 2018. ,
URL : https://hal.archives-ouvertes.fr/cea-02339457
Application of CUPID for subchannel-scale thermalehydraulic analysis of pressurized water reactor core under single-phase conditions, Nuclear Engineering and Technology, vol.50, pp.54-67, 2018. ,