Up to now, predicting accurately the Fission Gas Release (FGR) from high burn up UO2 and/or MOX (Mixed Oxide) fuels at off-normal conditions, such as power transient, reactivity-initiated accident (RIA) and loss-of-coolant accident (LOCA), is still a significant and very challenging task. For this purpose, different R&D programs have been carried out in France, as well as in other countries. This has been done with a specific emphasis on mechanisms which promote the FGR under accidental conditions. These studies can be performed thanks to dedicated integral experiments conducted in-pile (i.e. in Materials Testing Reactor) with the corresponding cost and constraints, or at the laboratory scale with annealing tests which allow to be represent...
To investigate the potential disintegration to powder of high burn-up fuel pellets during a rapid te...
An apparatus to study rare-gas fission-product release from nuclear fuel materials during postirradi...
The current research focuses on laser melting and successive analysis of laboratory-scale uranium di...
International audienceUp to now, predicting accurately the Fission Gas Release (FGR) from high burn ...
International audienceUnderstanding the behaviour of nuclear fuel materials in relation to the diffe...
International audienceUnderstanding the behavior of nuclear materials, regarding fission gas release...
<p>Major and severe accidents have occurred three times in nuclear power plants (NPPs), at Three Mil...
International audienceThe fission gas release (FGR) is a key point that must be accurately assessed ...
International audienceThe knowledge of materials properties and their behavior at high temperatures ...
Abstract –Fuel irradiation testing and post-irradiation examination are currently in progress as par...
To investigate the phenomenon of high burn-up fuel pellet material potentially disintegrating into p...
Understanding the behaviour of nuclear materials in extreme conditions is of prime importance for th...
To investigate the potential disintegration to powder of high burn-up fuel pellets during a rapid te...
An apparatus to study rare-gas fission-product release from nuclear fuel materials during postirradi...
The current research focuses on laser melting and successive analysis of laboratory-scale uranium di...
International audienceUp to now, predicting accurately the Fission Gas Release (FGR) from high burn ...
International audienceUnderstanding the behaviour of nuclear fuel materials in relation to the diffe...
International audienceUnderstanding the behavior of nuclear materials, regarding fission gas release...
<p>Major and severe accidents have occurred three times in nuclear power plants (NPPs), at Three Mil...
International audienceThe fission gas release (FGR) is a key point that must be accurately assessed ...
International audienceThe knowledge of materials properties and their behavior at high temperatures ...
Abstract –Fuel irradiation testing and post-irradiation examination are currently in progress as par...
To investigate the phenomenon of high burn-up fuel pellet material potentially disintegrating into p...
Understanding the behaviour of nuclear materials in extreme conditions is of prime importance for th...
To investigate the potential disintegration to powder of high burn-up fuel pellets during a rapid te...
An apparatus to study rare-gas fission-product release from nuclear fuel materials during postirradi...
The current research focuses on laser melting and successive analysis of laboratory-scale uranium di...