A direct-electrical-heating apparatus has been designed and fabricated to investigate those nuclear-fuel-related phenomena involved in the gap closure-bridging annulus formation mechanism that can be reproduced in an out-of-reactor environment. Prototypic light-water-reactor uranium dioxide fuel-pellet temperature profiles have been generated utilizing high flow rates (approximately 700 liters/min) of helium coolant gas, and a re-circulating system has been fabricated to permit tests of up to 1000 h. Simulated light-water-reactor single- and multiple-thermal-cycle experiments will be conducted on both unclad and ceramic (fused silica) clad uranium dioxide pellet stacks. A laser dilatometer is used to measure pellet dimensional increase cont...
The current research focuses on laser melting and successive analysis of laboratory-scale uranium di...
The effects of the thermally-induced cracking and subsequent relocation of UO/sub 2/ fuel pellets on...
En rampe de puissance, le combustible nucléaire est soumis à d'importantes contraintes thermiques e...
A variety of normal operation and accident scenarios can generate thermal stresses large enough to c...
International audienceUnderstanding the behavior of nuclear materials, regarding fission gas release...
Up to now, predicting accurately the Fission Gas Release (FGR) from high burn up UO2 and/or MOX (Mix...
Testing of two fuel clad specimens for thermionic reactor application is described. The annular UO2 ...
This study presents the peridynamic simulation of thermal cracking behaviour in uranium dioxide, UO2...
Due to the Fukushima nuclear accident there has been a large effort by several countries to develop ...
"Final report for research project sponsored by Northeast Utilities Service Company, Yankee Atomic E...
Fuel treatment is planned at the Argonne National Laboratory on EBR-II spent fuel. The electrochemic...
BS>A Zircaloy-clad tube of unalloyed uranium that was irradiated in a loop of the NRU reactor to a m...
A novel full scale production reactor fuel assembly model was designed and built to study thermal-hy...
Nuclear fuel undergoes various changes in its properties and composition as it is irradiated in a nu...
Fundamental experiments have been performed with a direct-electrical-heating apparatus, on both uncl...
The current research focuses on laser melting and successive analysis of laboratory-scale uranium di...
The effects of the thermally-induced cracking and subsequent relocation of UO/sub 2/ fuel pellets on...
En rampe de puissance, le combustible nucléaire est soumis à d'importantes contraintes thermiques e...
A variety of normal operation and accident scenarios can generate thermal stresses large enough to c...
International audienceUnderstanding the behavior of nuclear materials, regarding fission gas release...
Up to now, predicting accurately the Fission Gas Release (FGR) from high burn up UO2 and/or MOX (Mix...
Testing of two fuel clad specimens for thermionic reactor application is described. The annular UO2 ...
This study presents the peridynamic simulation of thermal cracking behaviour in uranium dioxide, UO2...
Due to the Fukushima nuclear accident there has been a large effort by several countries to develop ...
"Final report for research project sponsored by Northeast Utilities Service Company, Yankee Atomic E...
Fuel treatment is planned at the Argonne National Laboratory on EBR-II spent fuel. The electrochemic...
BS>A Zircaloy-clad tube of unalloyed uranium that was irradiated in a loop of the NRU reactor to a m...
A novel full scale production reactor fuel assembly model was designed and built to study thermal-hy...
Nuclear fuel undergoes various changes in its properties and composition as it is irradiated in a nu...
Fundamental experiments have been performed with a direct-electrical-heating apparatus, on both uncl...
The current research focuses on laser melting and successive analysis of laboratory-scale uranium di...
The effects of the thermally-induced cracking and subsequent relocation of UO/sub 2/ fuel pellets on...
En rampe de puissance, le combustible nucléaire est soumis à d'importantes contraintes thermiques e...