International audienceThe analysis of the PHEBUS FPT0 and FPT1 tests and some VERCORS tests performed under oxidising atmospheres with non irradiated (FPT0) and irradiated UO2 fuel evidenced that the fuel collapse temperature was well below the standard melting temperature of UO2 (3120 K) and above all lower than the 'eutectic' temperature of the UO2-ZrO2 pseudo-binary phase diagram (2820 K). Different assumptions as the role played by the fission products on the fuel degradation mechanism or the interaction between the structural materials and the fuel rods in the PHEBUS tests were advanced to explain a such behaviour. The fuel oxidation was also considered but on the basis of the old experimental data of Latta et al. , it was not retained...
International audienceDuring a severe accident in a pressurized water reactor, very high temperature...
AbstractRecently, novel container-less laser heating experimental data have been published on the me...
International audienceThe present study describes the in-situ electrochemical modifications which af...
International audienceThe analysis of the PHEBUS FPT0 and FPT1 tests and some VERCORS tests performe...
International audienceLiquidus and solidus temperatures were recently re-measured in the UO2+x compo...
International audienceOne objective of the FPT2 test of the PHEBUS FP Program was to study the degra...
AbstractThe present work highlights the importance, in nuclear fuel safety and performance, of the v...
International audienceThe fuel of civil nuclear plants, UO2, melts at 3120 K. During an hypothetical...
Recently, novel container-less laser heating experimental data have been published on the melting be...
Characterization of the fuel debris has been required for decommissioning Fukushima Daiichi Nuclear ...
During a severe nuclear accident, the UO2 fuel rods, Zircaloy cladding, guide tubes, absorber and st...
The objective of the Fuel Cycle R&D Program, Advanced Fuels campaign is to provide the research ...
The present work highlights the importance, in nuclear fuel safety and performance, of the very high...
Globally the most used nuclear fuel material is uranium(IV) oxide (UO2) and it is produced by powder...
Results for the radial distribution of the oxygen potential and stoichiometry of a PWR fuel with an ...
International audienceDuring a severe accident in a pressurized water reactor, very high temperature...
AbstractRecently, novel container-less laser heating experimental data have been published on the me...
International audienceThe present study describes the in-situ electrochemical modifications which af...
International audienceThe analysis of the PHEBUS FPT0 and FPT1 tests and some VERCORS tests performe...
International audienceLiquidus and solidus temperatures were recently re-measured in the UO2+x compo...
International audienceOne objective of the FPT2 test of the PHEBUS FP Program was to study the degra...
AbstractThe present work highlights the importance, in nuclear fuel safety and performance, of the v...
International audienceThe fuel of civil nuclear plants, UO2, melts at 3120 K. During an hypothetical...
Recently, novel container-less laser heating experimental data have been published on the melting be...
Characterization of the fuel debris has been required for decommissioning Fukushima Daiichi Nuclear ...
During a severe nuclear accident, the UO2 fuel rods, Zircaloy cladding, guide tubes, absorber and st...
The objective of the Fuel Cycle R&D Program, Advanced Fuels campaign is to provide the research ...
The present work highlights the importance, in nuclear fuel safety and performance, of the very high...
Globally the most used nuclear fuel material is uranium(IV) oxide (UO2) and it is produced by powder...
Results for the radial distribution of the oxygen potential and stoichiometry of a PWR fuel with an ...
International audienceDuring a severe accident in a pressurized water reactor, very high temperature...
AbstractRecently, novel container-less laser heating experimental data have been published on the me...
International audienceThe present study describes the in-situ electrochemical modifications which af...