The future HPRR LEU fuel plates will have to withstand aggressive irradiations leading to a swelling phenomenon. This latter induces structure modifications and impacts the initial inter-plate distance. This distance is investigated, under the access and microscopic resolution constraints, within the PERSEUS Project aiming the development of a non-destructive ultrasonic device. With a thickness of 1 mm to be inserted into the 1.8 mm water channel width of the High flux Reactor (RHF), the device relies upon two ultrasonic transducers connected to an electronic system. It allows time of flight and ultrasonic velocity estimations. The feasibility being already proved, optimizations on components of the measurement chain and signal processing h...
National audienceThe in-service inspection of internal structures of future liquid sodium-cooled fas...
To predict the performance of nuclear fuels and materials, irradiated fuel plates must be characteri...
The focus of the present thesis is the determination of the elastic properties of nuclear fuel using...
The future HPRR LEU fuel plates will have to withstand aggressive irradiations leading to a swelling...
The fuel elements of High Performance and Research Reactors are usually made of plates instead of ro...
International audienceMost of the High Performance Research Reactors (HPRR) are made of plates under...
AbstractMost high flux reactors for research purposes have fuel elements composed of plates and not ...
AbstractMost high flux reactors possess for research purposes fuel elements composed of plates. Thei...
International audienceMost high flux reactors for research purposes have fuel elements composed of p...
The fuel element plates of research reactors are subjected to swelling phenomena. These structure mo...
The goal of this study is to realize an ultrasonic sensor for pressure and composition of released f...
Nuclear fuel is the core component of reactors that is used to produce the neutron flux required for...
AbstractThe purpose of the presented work was to undertake experimental trials to demonstrate the po...
The purpose of the presented work was to undertake experimental trials to demonstrate the potential ...
In the sodium-cooled fast reactor (SFR), conventional optical visual inspections cannot be applied d...
National audienceThe in-service inspection of internal structures of future liquid sodium-cooled fas...
To predict the performance of nuclear fuels and materials, irradiated fuel plates must be characteri...
The focus of the present thesis is the determination of the elastic properties of nuclear fuel using...
The future HPRR LEU fuel plates will have to withstand aggressive irradiations leading to a swelling...
The fuel elements of High Performance and Research Reactors are usually made of plates instead of ro...
International audienceMost of the High Performance Research Reactors (HPRR) are made of plates under...
AbstractMost high flux reactors for research purposes have fuel elements composed of plates and not ...
AbstractMost high flux reactors possess for research purposes fuel elements composed of plates. Thei...
International audienceMost high flux reactors for research purposes have fuel elements composed of p...
The fuel element plates of research reactors are subjected to swelling phenomena. These structure mo...
The goal of this study is to realize an ultrasonic sensor for pressure and composition of released f...
Nuclear fuel is the core component of reactors that is used to produce the neutron flux required for...
AbstractThe purpose of the presented work was to undertake experimental trials to demonstrate the po...
The purpose of the presented work was to undertake experimental trials to demonstrate the potential ...
In the sodium-cooled fast reactor (SFR), conventional optical visual inspections cannot be applied d...
National audienceThe in-service inspection of internal structures of future liquid sodium-cooled fas...
To predict the performance of nuclear fuels and materials, irradiated fuel plates must be characteri...
The focus of the present thesis is the determination of the elastic properties of nuclear fuel using...