The implementation and validation of multi-dimensional (multi-D) features in thermal-hydraulic system codes aims to extend the application of these codes towards multi-scale simulations. The main goal is the simulation of large-scale three-dimensional effects inside large volumes such as piping or vessel. This novel approach becomes especially relevant during the simulation of accidents with strongly asymmetric flow conditions entailing density gradients. Under such conditions, coolant mixing is a key phenomenon on the eventual variation of the coolant temperature and/or boron concentration at the core inlet and on the extent of a local re-criticality based on the reactivity feedback effects. This approach presents several advantages compar...
International audiencePhénix is a French pool-type sodium-cooled prototype reactor; before the defin...
The reactor dynamics codes for transient and accident analyses inherently include the coupling of ne...
Rising computational capabilities have allowed for the possibility of more complex thermal hydraulic...
In the present study, the 3-D features of the thermal-hydraulic system code CATHARE2 were thoroughly...
The MSLB (Main Steam Line Break) accident scenario is one of the severe abnormal transients that mig...
The mixing phenomenon is relevant for the normal and off normal operation of the Nuclear Power Plant...
Modeling and numerical simulation of transient thermal-hydraulic phenomena in pool-type systems, suc...
International audienceThis work has been performed in the framework of the OECD-NEA thermalhydraulic...
In a pool-type liquid metal cooled reactor like MYRRHA, the influence of 3-D thermal-hydraulic pheno...
International audienceSystem thermalhydraulic (SYS-TH) codes are extensively used for Design Basis A...
System thermalhydraulic codes remain the main tool for nuclear reactor design and safety issues. How...
Coolant mixing under natural circulation flow regime constitutes a key parameter that may play a rol...
The objective of this PhD is to asses the capability of Computational Fluid Dynamics (CFD) to predic...
International audienceIn the framework of the 4th-generation sodium fast reactor ASTRID, numerical s...
MYRRHA (Multi-purpose hybrid research reactor for high-tech applications) is a lead-bismuth eutectic...
International audiencePhénix is a French pool-type sodium-cooled prototype reactor; before the defin...
The reactor dynamics codes for transient and accident analyses inherently include the coupling of ne...
Rising computational capabilities have allowed for the possibility of more complex thermal hydraulic...
In the present study, the 3-D features of the thermal-hydraulic system code CATHARE2 were thoroughly...
The MSLB (Main Steam Line Break) accident scenario is one of the severe abnormal transients that mig...
The mixing phenomenon is relevant for the normal and off normal operation of the Nuclear Power Plant...
Modeling and numerical simulation of transient thermal-hydraulic phenomena in pool-type systems, suc...
International audienceThis work has been performed in the framework of the OECD-NEA thermalhydraulic...
In a pool-type liquid metal cooled reactor like MYRRHA, the influence of 3-D thermal-hydraulic pheno...
International audienceSystem thermalhydraulic (SYS-TH) codes are extensively used for Design Basis A...
System thermalhydraulic codes remain the main tool for nuclear reactor design and safety issues. How...
Coolant mixing under natural circulation flow regime constitutes a key parameter that may play a rol...
The objective of this PhD is to asses the capability of Computational Fluid Dynamics (CFD) to predic...
International audienceIn the framework of the 4th-generation sodium fast reactor ASTRID, numerical s...
MYRRHA (Multi-purpose hybrid research reactor for high-tech applications) is a lead-bismuth eutectic...
International audiencePhénix is a French pool-type sodium-cooled prototype reactor; before the defin...
The reactor dynamics codes for transient and accident analyses inherently include the coupling of ne...
Rising computational capabilities have allowed for the possibility of more complex thermal hydraulic...