International audienceThe interactions of iodine and caesium in UO2 have been investigated. For this purpose, implanted UO2 samples were thermally treated (4h at 900°C or 1h at 1200°C) under controlled atmosphere (0.03% H2O/H2) and then characterized by several experimental techniques for their structural and chemical studies. Thermodynamic calculations were also performed in order to optimize heat treatment conditions before performing tests, and to help in the interpretation of results afterwards. The sample characterizations after thermal treatments reveal the presence of bubbles and precipitates (mean diameter around 10 - 20 nm) and have allowed to clearly identify the presence of CsI in these bubbles which is in agreement with the calc...
International audienceThe development of realistic models for fission products behavior during a nuc...
Brief presentation of the research lead at VTT on fission products transport and chemistry was made,...
In the case of a severe nuclear reactor accident, UO2 particles may be emitted as a consequence of m...
International audienceThe interactions of iodine and caesium in UO2 have been investigated. For this...
En transitoire de puissance, le combustible nucléaire des Réacteurs à Eau Pressurisée (REP) est soum...
International audienceThis study aims to evaluate the influence of a metallic fission product, molyb...
The behaviour and release of fission products during high-temperature annealing of irradiated UO2 sa...
During a power transient, the nuclear fuel of Pressurized Water Reactors (PWR) undergoes major tempe...
The objective of this work was to study the molybdenum chemistry in UO2 based materials, known as SI...
International audienceAn inter-laboratory comparison has provided enhanced confidence in a novel out...
International audienceUnder irradiations in nuclear reactors, the microstructure of oxide nuclear fu...
International audienceTransmission electron microscopy (TEM) experiments were performed, on a set Of...
Supported by results of calculations performed with two analytical tools (MFPR, which takes account ...
A high temperature reaction process was involved with the dry treatment of spent nuclear fuels (SNFs...
International audienceThe development of realistic models for fission products behavior during a nuc...
Brief presentation of the research lead at VTT on fission products transport and chemistry was made,...
In the case of a severe nuclear reactor accident, UO2 particles may be emitted as a consequence of m...
International audienceThe interactions of iodine and caesium in UO2 have been investigated. For this...
En transitoire de puissance, le combustible nucléaire des Réacteurs à Eau Pressurisée (REP) est soum...
International audienceThis study aims to evaluate the influence of a metallic fission product, molyb...
The behaviour and release of fission products during high-temperature annealing of irradiated UO2 sa...
During a power transient, the nuclear fuel of Pressurized Water Reactors (PWR) undergoes major tempe...
The objective of this work was to study the molybdenum chemistry in UO2 based materials, known as SI...
International audienceAn inter-laboratory comparison has provided enhanced confidence in a novel out...
International audienceUnder irradiations in nuclear reactors, the microstructure of oxide nuclear fu...
International audienceTransmission electron microscopy (TEM) experiments were performed, on a set Of...
Supported by results of calculations performed with two analytical tools (MFPR, which takes account ...
A high temperature reaction process was involved with the dry treatment of spent nuclear fuels (SNFs...
International audienceThe development of realistic models for fission products behavior during a nuc...
Brief presentation of the research lead at VTT on fission products transport and chemistry was made,...
In the case of a severe nuclear reactor accident, UO2 particles may be emitted as a consequence of m...