International audienceIn this paper, we performed a four-dimensional numerical simulation to calculate wave propagation in a thermal fluctuating liquid metal in order to obtain detailed knowledge on a wave propagation in coolant material of a Sodium-cooled Fast reactor (SFR). The wave and the medium are described in three spatial and one temporal dimensions. We made use of a massive data set to describe the fluctuating situation of the medium. This data set was provided by Computational Fluid Dynamics (CFD) with a Large-Eddy Simulation (LES) model, which calculated the temperature field with a higher spatial resolution than Reynolds-Averaged Navier–Stokes turbulence models (RANS). This data set was furthermore obtained from other studies on a...
International audienceIn the framework of the French R&D program for the Generation IV reactors ...
International audienceIn the framework of the French R&D program for the Generation IV reactors ...
International audienceIn the framework of the French R&D program for the Generation IV reactors ...
International audienceIn this paper, we performed a four-dimensional numerical simulation to calcula...
ASTRID project, French sodium cooled nuclear reactor of 4th generation, is under development at the ...
ASTRID project, French sodium cooled nuclear reactor of 4th generation, is under development at the ...
International audienceThe simulation of the propagation of ultrasonic waves in a moving fluid will i...
International audienceThe simulation of the propagation of ultrasonic waves in a moving fluid will i...
International audienceThe simulation of the propagation of ultrasonic waves in a moving fluid will i...
International audienceThe simulation of the propagation of ultrasonic waves in a moving fluid will i...
WOS:000337143500105International audienceThe use of ultrasonic instrumentation in sodium-cooled fast...
WOS:000337143500105International audienceThe use of ultrasonic instrumentation in sodium-cooled fast...
WOS:000337143500105International audienceThe use of ultrasonic instrumentation in sodium-cooled fast...
International audienceWe study the development potential of ultrasonic thermometry in a liquid fluct...
International audienceWe study the development potential of ultrasonic thermometry in a liquid fluct...
International audienceIn the framework of the French R&D program for the Generation IV reactors ...
International audienceIn the framework of the French R&D program for the Generation IV reactors ...
International audienceIn the framework of the French R&D program for the Generation IV reactors ...
International audienceIn this paper, we performed a four-dimensional numerical simulation to calcula...
ASTRID project, French sodium cooled nuclear reactor of 4th generation, is under development at the ...
ASTRID project, French sodium cooled nuclear reactor of 4th generation, is under development at the ...
International audienceThe simulation of the propagation of ultrasonic waves in a moving fluid will i...
International audienceThe simulation of the propagation of ultrasonic waves in a moving fluid will i...
International audienceThe simulation of the propagation of ultrasonic waves in a moving fluid will i...
International audienceThe simulation of the propagation of ultrasonic waves in a moving fluid will i...
WOS:000337143500105International audienceThe use of ultrasonic instrumentation in sodium-cooled fast...
WOS:000337143500105International audienceThe use of ultrasonic instrumentation in sodium-cooled fast...
WOS:000337143500105International audienceThe use of ultrasonic instrumentation in sodium-cooled fast...
International audienceWe study the development potential of ultrasonic thermometry in a liquid fluct...
International audienceWe study the development potential of ultrasonic thermometry in a liquid fluct...
International audienceIn the framework of the French R&D program for the Generation IV reactors ...
International audienceIn the framework of the French R&D program for the Generation IV reactors ...
International audienceIn the framework of the French R&D program for the Generation IV reactors ...