In the scheme of French ASTRID (Advanced Sodium Technological Reactor for Industrial Demonstration) project, fluid-structure interaction phenomena involved in the dynamic behaviour of core flowering, which could happen during seismic events, are of high interest. Also core flowering behaviour is considered as the main initiating event for the four SCRAMs that happened in Phénix reactor during 1989 and 1990. In objective to improve the knowledge of fluid-structure interaction phenomena of dynamic issues in a SFR core, especially focused on damping, this Ph.D. thesis have been conducted in experimental, numerical and analytical approaches based on free-vibration experiments on mono-assembly test facility PISE-1A and multi-assembly test facili...
A safety vessel is incorporated in the sodium cooled fast reactors surrounding the main vessel to co...
In nuclear power plants, steam generator tubes vibrate because of steam/water cross-flows. In order ...
Les générateurs de vapeur (GV) sont l’un des com-posants majeurs des réacteurs nucléaires, et une co...
In the scheme of French ASTRID (Advanced Sodium Technological Reactor for Industrial Demonstration) ...
The purpose of this study is to improve the knowledge about the core behavior of a sodium fast breed...
Cette thèse vise à améliorer la compréhension du comportement d’un cœur de réacteur à neutrons rapid...
International audienceIn the scheme of French ASTRID (Advanced Sodium TechnologicalReactor for Indus...
Dynamic experiments in air and water (simulating liquid sodium) were performed by ISMES, on behalf o...
Efficient modelling and accurate knowledge of the mechanical behaviour of the reactorcore are needed...
Due to the high confinement of the closed fuel assemblies in Sodium-cooled Fast Reactors (SFR), the ...
International audienceThe present paper deals with a numerical modeling of a nuclear reactor with fl...
Dans le cadre des études de sûreté, il est nécessaire de disposer de modèles validés des forces flui...
The designing of a pressurized water reactor core subjected to seismic loading, is a major concern o...
This work concerns the assessment of the consequences deriving from a Hypothetical Core Disruptive A...
The results of dynamic experiments on shaking tables, carried out in water (simulating sodium) on bo...
A safety vessel is incorporated in the sodium cooled fast reactors surrounding the main vessel to co...
In nuclear power plants, steam generator tubes vibrate because of steam/water cross-flows. In order ...
Les générateurs de vapeur (GV) sont l’un des com-posants majeurs des réacteurs nucléaires, et une co...
In the scheme of French ASTRID (Advanced Sodium Technological Reactor for Industrial Demonstration) ...
The purpose of this study is to improve the knowledge about the core behavior of a sodium fast breed...
Cette thèse vise à améliorer la compréhension du comportement d’un cœur de réacteur à neutrons rapid...
International audienceIn the scheme of French ASTRID (Advanced Sodium TechnologicalReactor for Indus...
Dynamic experiments in air and water (simulating liquid sodium) were performed by ISMES, on behalf o...
Efficient modelling and accurate knowledge of the mechanical behaviour of the reactorcore are needed...
Due to the high confinement of the closed fuel assemblies in Sodium-cooled Fast Reactors (SFR), the ...
International audienceThe present paper deals with a numerical modeling of a nuclear reactor with fl...
Dans le cadre des études de sûreté, il est nécessaire de disposer de modèles validés des forces flui...
The designing of a pressurized water reactor core subjected to seismic loading, is a major concern o...
This work concerns the assessment of the consequences deriving from a Hypothetical Core Disruptive A...
The results of dynamic experiments on shaking tables, carried out in water (simulating sodium) on bo...
A safety vessel is incorporated in the sodium cooled fast reactors surrounding the main vessel to co...
In nuclear power plants, steam generator tubes vibrate because of steam/water cross-flows. In order ...
Les générateurs de vapeur (GV) sont l’un des com-posants majeurs des réacteurs nucléaires, et une co...