International audienceThe new MEXIICO experimental loop has recently been started in the LECA-STAR hot-cell facility of the CEA Cadarache. It is dedicated to the understanding of the basic mechanisms occurring in nuclear fuels during nuclear reactor power transients and accidental situations. Under such conditions the nuclear fuels are submitted to thermo-mechanical stresses. These stresses play a major role on fission product release and fuel fragmentation. Evaluating such fuel behavior represents a key issue for reactor safety analyses.In the first part of the paper, we describe the complete MEXIICO device, which main component is a hot isostatic press allowing to perform analytical experiments in the [20°C -1600°C / 10 MPa - 160 MPa] reg...
International audienceDespite the very high level of control and safety in Nuclear Power Plant, they...
The High Temperature Reactor (HTR) is characterised by an advanced design with passive safety featur...
International audienceUnder LOCA conditions, the temperature gradient evolution within the fuel pell...
International audienceThe new MEXIICO experimental loop has recently been started in the LECA-STAR h...
International audienceThe MEXIICO project carried out by the CEA and supported by EDF and AREVA has ...
To investigate the phenomenon of high burn-up fuel pellet material potentially disintegrating into p...
The ceramic and ceramic-like coating materials in modern high-temperature reactor fuel are designed ...
In oxide nuclear fuels, at high burn-up or during high temperature periods such as ramp tests, out-o...
Up to now, predicting accurately the Fission Gas Release (FGR) from high burn up UO2 and/or MOX (Mix...
International audienceThe industrial fission gas behavior model CARACAS developed and validated for ...
International audienceUnderstanding the behavior of nuclear materials, regarding fission gas release...
Nuclear fuel undergoes various changes in its properties and composition as it is irradiated in a nu...
This paper presents simulations of four tests performed on medium to high burnup fuel during the VER...
The Cold Finger Apparatus (KühlFinger-Apparatur – KüFA) in operation at JRC-ITU is designed to exper...
To investigate the potential disintegration to powder of high burn-up fuel pellets during a rapid te...
International audienceDespite the very high level of control and safety in Nuclear Power Plant, they...
The High Temperature Reactor (HTR) is characterised by an advanced design with passive safety featur...
International audienceUnder LOCA conditions, the temperature gradient evolution within the fuel pell...
International audienceThe new MEXIICO experimental loop has recently been started in the LECA-STAR h...
International audienceThe MEXIICO project carried out by the CEA and supported by EDF and AREVA has ...
To investigate the phenomenon of high burn-up fuel pellet material potentially disintegrating into p...
The ceramic and ceramic-like coating materials in modern high-temperature reactor fuel are designed ...
In oxide nuclear fuels, at high burn-up or during high temperature periods such as ramp tests, out-o...
Up to now, predicting accurately the Fission Gas Release (FGR) from high burn up UO2 and/or MOX (Mix...
International audienceThe industrial fission gas behavior model CARACAS developed and validated for ...
International audienceUnderstanding the behavior of nuclear materials, regarding fission gas release...
Nuclear fuel undergoes various changes in its properties and composition as it is irradiated in a nu...
This paper presents simulations of four tests performed on medium to high burnup fuel during the VER...
The Cold Finger Apparatus (KühlFinger-Apparatur – KüFA) in operation at JRC-ITU is designed to exper...
To investigate the potential disintegration to powder of high burn-up fuel pellets during a rapid te...
International audienceDespite the very high level of control and safety in Nuclear Power Plant, they...
The High Temperature Reactor (HTR) is characterised by an advanced design with passive safety featur...
International audienceUnder LOCA conditions, the temperature gradient evolution within the fuel pell...