Volatile fission products release during thermal annealing of UO2 fuels irradiated at different burnup and temperature has been measured with a Knudsen cell mass spectrometer system. The release kinetics and the semi quantitative analysis of the fission products have been performed for burnup ranging from 27 to 240 GWd/Ty, and for irradiation temperatures ranging from 500 to 1200 aC. The microstructure of the samples at end of irradiation and after the laboratoiy annealing tests has been studied by scanning and by transmission electron microscopy. The thermal release profiles have been interpreted based on the original microstructure as well as on the evolution of this microstructure during heating.JRC.E.3-Materials researc
Gaseous fission product generation, transport, and release can have a large impact on nuclear fuel p...
International audienceDuring the irradiation of nuclear fuel in a light water reactor (LWR), fission...
The chemical form and rate of release of volatile fission products (i.e., Xe, Kr, Cs, Te, I...) effu...
The behaviour and release of fission products during high-temperature annealing of irradiated UO2 sa...
A commercial PWR fuel sample with a local burn-up of about 240 MWd/kgHM was annealed in a Knudsen ce...
International audienceUnder irradiations in nuclear reactors, the microstructure of oxide nuclear fu...
The evolution of fission products from UO/sub 2/ during irradiation at high temperatures is of prima...
For the efficient operation of LWR MOX fuels, burnup extension of MOX fuels up to the same burnup le...
Irradiated LWR fuel from the BR3 reactor was thermally annealed up to 2500 K in a Knudsen-cell, and ...
Thermal recovery of radiation defects and microstructural change in UOfuels irradiated under LWR con...
Oxidation of UO2 fuel under off-normal and normal reactor conditions occurs when fuel cladding fails...
Samples of irradiated MOX of 44 GWd/tHM mean burn-up were prepared by core drilling at three differe...
3.00SIGLELD:9091.9F(ND-R--720(W)) / BLDSC - British Library Document Supply CentreGBUnited Kingdo
A BWR design UO2 fuel irradiated to a burnup of 7.9% FIMA was selected for a careful calculational a...
The instant release of fission products from high burn-up UO2 fuels and one MOX fuel was investigate...
Gaseous fission product generation, transport, and release can have a large impact on nuclear fuel p...
International audienceDuring the irradiation of nuclear fuel in a light water reactor (LWR), fission...
The chemical form and rate of release of volatile fission products (i.e., Xe, Kr, Cs, Te, I...) effu...
The behaviour and release of fission products during high-temperature annealing of irradiated UO2 sa...
A commercial PWR fuel sample with a local burn-up of about 240 MWd/kgHM was annealed in a Knudsen ce...
International audienceUnder irradiations in nuclear reactors, the microstructure of oxide nuclear fu...
The evolution of fission products from UO/sub 2/ during irradiation at high temperatures is of prima...
For the efficient operation of LWR MOX fuels, burnup extension of MOX fuels up to the same burnup le...
Irradiated LWR fuel from the BR3 reactor was thermally annealed up to 2500 K in a Knudsen-cell, and ...
Thermal recovery of radiation defects and microstructural change in UOfuels irradiated under LWR con...
Oxidation of UO2 fuel under off-normal and normal reactor conditions occurs when fuel cladding fails...
Samples of irradiated MOX of 44 GWd/tHM mean burn-up were prepared by core drilling at three differe...
3.00SIGLELD:9091.9F(ND-R--720(W)) / BLDSC - British Library Document Supply CentreGBUnited Kingdo
A BWR design UO2 fuel irradiated to a burnup of 7.9% FIMA was selected for a careful calculational a...
The instant release of fission products from high burn-up UO2 fuels and one MOX fuel was investigate...
Gaseous fission product generation, transport, and release can have a large impact on nuclear fuel p...
International audienceDuring the irradiation of nuclear fuel in a light water reactor (LWR), fission...
The chemical form and rate of release of volatile fission products (i.e., Xe, Kr, Cs, Te, I...) effu...