Samples of irradiated MOX of 44 GWd/tHM mean burn-up were prepared by core drilling at three different radial positions of a fuel pellet. They were subsequently heated in a Knudsen effusion mass spectrometry system up to complete vaporization of the sample (~2600 K) and the release of fission gas (krypton and xenon) and helium was measured. Scanning electron microscopy was used in parallel to investigate the evolution of the microstructure of a sample heated in the same condition up to given key temperatures as determined from the gas release profiles. A clear difference for fission gas release and microstructure was observed as a function of the radial position of the samples and therefore of irradiation temperature. A good correlation bet...
Irradiated LWR fuel from the BR3 reactor was thermally annealed up to 2500 K in a Knudsen-cell, and ...
It is important to understand fission-product (FP) and kernel micro-structure evolution in TRISO-coa...
The chemical form and rate of release of volatile fission products (i.e., Xe, Kr, Cs, Te, I...) effu...
A commercial PWR fuel sample with a local burn-up of about 240 MWd/kgHM was annealed in a Knudsen ce...
For the efficient operation of LWR MOX fuels, burnup extension of MOX fuels up to the same burnup le...
Volatile fission products release during thermal annealing of UO2 fuels irradiated at different burn...
Two sections of OCOM fuel were investigated. In one fuel the MOX agglomerates contained 18 w% fissil...
A particular low temperature behaviour of the 131Xe isotope was observed during release studies of f...
Recent electron microscopy investigations are presented with emphasis on properties related to the s...
The instant release of fission products from high burn-up UO2 fuels and one MOX fuel was investigate...
International audienceUnder irradiations in nuclear reactors, the microstructure of oxide nuclear fu...
International audienceDuring the irradiation of nuclear fuel in a light water reactor (LWR), fission...
Understanding the microstructural and phase changes occurring during irradiation and their impact on...
The behaviour and release of fission products during high-temperature annealing of irradiated UO2 sa...
The Advanced Fuels Campaign performed a series of irradiation tests of minor actinide-bearing mixed ...
Irradiated LWR fuel from the BR3 reactor was thermally annealed up to 2500 K in a Knudsen-cell, and ...
It is important to understand fission-product (FP) and kernel micro-structure evolution in TRISO-coa...
The chemical form and rate of release of volatile fission products (i.e., Xe, Kr, Cs, Te, I...) effu...
A commercial PWR fuel sample with a local burn-up of about 240 MWd/kgHM was annealed in a Knudsen ce...
For the efficient operation of LWR MOX fuels, burnup extension of MOX fuels up to the same burnup le...
Volatile fission products release during thermal annealing of UO2 fuels irradiated at different burn...
Two sections of OCOM fuel were investigated. In one fuel the MOX agglomerates contained 18 w% fissil...
A particular low temperature behaviour of the 131Xe isotope was observed during release studies of f...
Recent electron microscopy investigations are presented with emphasis on properties related to the s...
The instant release of fission products from high burn-up UO2 fuels and one MOX fuel was investigate...
International audienceUnder irradiations in nuclear reactors, the microstructure of oxide nuclear fu...
International audienceDuring the irradiation of nuclear fuel in a light water reactor (LWR), fission...
Understanding the microstructural and phase changes occurring during irradiation and their impact on...
The behaviour and release of fission products during high-temperature annealing of irradiated UO2 sa...
The Advanced Fuels Campaign performed a series of irradiation tests of minor actinide-bearing mixed ...
Irradiated LWR fuel from the BR3 reactor was thermally annealed up to 2500 K in a Knudsen-cell, and ...
It is important to understand fission-product (FP) and kernel micro-structure evolution in TRISO-coa...
The chemical form and rate of release of volatile fission products (i.e., Xe, Kr, Cs, Te, I...) effu...