International audienceASTRID is a project for an industrial prototype of a 600 MWesodium cooled Fast Reactor, led by CEA. A consequent program is inprogress for the development and the validation of numerical toolsfor the simulation of the dynamic mechanical behavior of the FastReactor cores, with both experimental and numerical parts. The coresare constituted of Fuel Assemblies (or FA) and Neutronic Shields (orNS) immersed in the primary coolant (sodium), which circulatesinside the Fluid Assemblies. The FA and the NS are slenderstructures, which may be considered as beams, from a mechanicalpoint of view.The dynamic behavior of this system has to be understood, for designand safety studies. Two main movements have to be consideredglobal hor...
The need for energy is growing in the world and the market of nuclear power is now once more expandi...
Experimental results from the unprotected phase of the Natural Convection (NC) Test performed in the...
This paper deals with the interpretation of the neutron noise measurements in sodium-cooled fast neu...
International audienceASTRID is a project for an industrial prototype of a 600 MWesodium cooled Fast...
International audienceASTRID is a project for an industrial prototype of a 600 MWesodium cooled Fast...
The results of dynamic experiments on shaking tables, carried out in water (simulating sodium) on bo...
Dynamic experiments in air and water (simulating liquid sodium) were performed by ISMES, on behalf o...
The purpose of this study is to improve the knowledge about the core behavior of a sodium fast breed...
In this paper, a reactor core thermomechanical analysis method is described to provide a tool to qua...
The fuel assemblies of high-speed sodium-cooled reactors are an important component which operates u...
International audienceIn the scheme of French ASTRID (Advanced Sodium TechnologicalReactor for Indus...
Due to the high confinement of the closed fuel assemblies in Sodium-cooled Fast Reactors (SFR), the ...
International audienceWithin the framework of the Generation IV Sodium-cooled Fast Reactors (SFR) R ...
The core of Prototype Fast Breeder Reactor (PFBR) is designed to produce 1250 MWt at full power. PFB...
International audienceAccurate knowledge of the mechanical behaviour of the reactor core is needed t...
The need for energy is growing in the world and the market of nuclear power is now once more expandi...
Experimental results from the unprotected phase of the Natural Convection (NC) Test performed in the...
This paper deals with the interpretation of the neutron noise measurements in sodium-cooled fast neu...
International audienceASTRID is a project for an industrial prototype of a 600 MWesodium cooled Fast...
International audienceASTRID is a project for an industrial prototype of a 600 MWesodium cooled Fast...
The results of dynamic experiments on shaking tables, carried out in water (simulating sodium) on bo...
Dynamic experiments in air and water (simulating liquid sodium) were performed by ISMES, on behalf o...
The purpose of this study is to improve the knowledge about the core behavior of a sodium fast breed...
In this paper, a reactor core thermomechanical analysis method is described to provide a tool to qua...
The fuel assemblies of high-speed sodium-cooled reactors are an important component which operates u...
International audienceIn the scheme of French ASTRID (Advanced Sodium TechnologicalReactor for Indus...
Due to the high confinement of the closed fuel assemblies in Sodium-cooled Fast Reactors (SFR), the ...
International audienceWithin the framework of the Generation IV Sodium-cooled Fast Reactors (SFR) R ...
The core of Prototype Fast Breeder Reactor (PFBR) is designed to produce 1250 MWt at full power. PFB...
International audienceAccurate knowledge of the mechanical behaviour of the reactor core is needed t...
The need for energy is growing in the world and the market of nuclear power is now once more expandi...
Experimental results from the unprotected phase of the Natural Convection (NC) Test performed in the...
This paper deals with the interpretation of the neutron noise measurements in sodium-cooled fast neu...