The microstructure of the fuel pellet plays an essential role in fission gas buildup and release and is critical for the safe and continued operation of nuclear power stations. Structural analysis of uranium dioxide (UO2)–molybdenum (Mo) composite fuel pellets prepared at a range of sintering temperatures from 1300 to 1800 °C was performed. Mo micro and nanoparticles were used in making the composite pellets. A systematic investigation into the influence of processing parameters during Spark Plasma Sintering (SPS) of the pellets on the microstructure, texture, grain size, and grain boundary characters of UO2-Mo is presented. UO2-Mo composite show significant differences in the fraction of general boundaries and also special/coincident site ...
During its lifetime in the core of a nuclear reactor, the fuel undergoes significant changes in its ...
The sol-gel method, which is among the methods used for the production of ThO₂-UO₂ mixed oxide fuel ...
International audienceFour batches of UO2 pellets were studied comparatively, before and after creep...
Nuclear fuel performance under normal operating conditions and extreme accident conditions have stud...
Nuclear energy continues to play a large role in the energy landscape of the world. Of particular in...
The objectives of this paper is to report that the powder characteristics of uranium dioxides effect...
The context of this study is about increasing the performances of nuclear fuel used in existing nucl...
International audienceSignificant progresses in the performances under in-pile irradiation of partic...
As world electricity demands increase, nuclear energy can be a consistent, carbon-free energy source...
Understanding the microstructural and phase changes occurring during irradiation and their impact on...
Advanced Technology Fuels (ATF) harness the potential to increase safety at nuclear reactors by bols...
Cette thèse participe au développement d’un combustible particulaire uranium-molybdène dans le cadre...
Uranium nitride (UN)-uranium dioxide (UO2) composite fuels are being considered as an accident toler...
The fabricability of dispersion fuels using UO/sub 2/ or UC as the dispersoid and uranium combined w...
The sol-gel method, which is among the methods used for the production of ThO2-UO2 mixed oxide fuel ...
During its lifetime in the core of a nuclear reactor, the fuel undergoes significant changes in its ...
The sol-gel method, which is among the methods used for the production of ThO₂-UO₂ mixed oxide fuel ...
International audienceFour batches of UO2 pellets were studied comparatively, before and after creep...
Nuclear fuel performance under normal operating conditions and extreme accident conditions have stud...
Nuclear energy continues to play a large role in the energy landscape of the world. Of particular in...
The objectives of this paper is to report that the powder characteristics of uranium dioxides effect...
The context of this study is about increasing the performances of nuclear fuel used in existing nucl...
International audienceSignificant progresses in the performances under in-pile irradiation of partic...
As world electricity demands increase, nuclear energy can be a consistent, carbon-free energy source...
Understanding the microstructural and phase changes occurring during irradiation and their impact on...
Advanced Technology Fuels (ATF) harness the potential to increase safety at nuclear reactors by bols...
Cette thèse participe au développement d’un combustible particulaire uranium-molybdène dans le cadre...
Uranium nitride (UN)-uranium dioxide (UO2) composite fuels are being considered as an accident toler...
The fabricability of dispersion fuels using UO/sub 2/ or UC as the dispersoid and uranium combined w...
The sol-gel method, which is among the methods used for the production of ThO2-UO2 mixed oxide fuel ...
During its lifetime in the core of a nuclear reactor, the fuel undergoes significant changes in its ...
The sol-gel method, which is among the methods used for the production of ThO₂-UO₂ mixed oxide fuel ...
International audienceFour batches of UO2 pellets were studied comparatively, before and after creep...