In the pyroprocess integrated inactive demonstration (PRIDE) facility at the Korea Atomic Energy Research Institute (KAERI), UO2 porous pellets were fabricated as a feed material for electrolytic reduction on an engineering scale of 30 kg-U/batch. To increase the batch size, we designed and modified the corresponding equipment for unit processes based on ceramic processing. In the course of pellet fabrication, the correlation between the green density and sintered density was investigated within a compaction pressure range of 106–206 MPa, in terms of the optimization of processing parameters. Analysis of the microstructures of the produced UO2 porous pellets suggested that the pellets were suitable for feed material in the subsequent electr...
Most types of nuclear power reactors use fuel in the form of high density-uranium dioxide pellets cl...
This study is devoted to synthesis and characterization of uranium dioxide microspheres (Ø < 100 μm)...
Globally the most used nuclear fuel material is uranium(IV) oxide (UO2) and it is produced by powder...
Powder-free sol-gel microsphere pelletisation and low temperature (1473 K) oxidative sintering proce...
Progress in the development of manufacturing procedures and techniques for uranium dioxide fuel pell...
The actual tendency all over the world is to manufacture fuel bundles capable to resist high burn-up...
Pacific Northwest Laboratory (PNL) has evaluted, on a laboratory scale, the characteristics and pell...
Nuclear energy continues to play a large role in the energy landscape of the world. Of particular in...
The effects of a powder treatment, the sintering temperature and the sintering time on the grain gro...
The actual tendency all over the world is to manufacture fuel bundles capable to resist high burn-up...
Hydrated gel-microspheres of U, Pu, Th oxide or oxide plus carbon mixture of diameter 400-800µ ...
International audienceU1-xAmxO2±δ mixed-oxides are considered as promising compounds for americium h...
International audienceU$_{1-x}$Am$_x$O$_{2\pm\sigma}$ mixed-oxides are considered as promising compo...
The sol-gel method, which is among the methods used for the production of ThO2-UO2 mixed oxide fuel ...
The External Gelation of Uranium (EGU) process, though originally developed for preparation of fuel ...
Most types of nuclear power reactors use fuel in the form of high density-uranium dioxide pellets cl...
This study is devoted to synthesis and characterization of uranium dioxide microspheres (Ø < 100 μm)...
Globally the most used nuclear fuel material is uranium(IV) oxide (UO2) and it is produced by powder...
Powder-free sol-gel microsphere pelletisation and low temperature (1473 K) oxidative sintering proce...
Progress in the development of manufacturing procedures and techniques for uranium dioxide fuel pell...
The actual tendency all over the world is to manufacture fuel bundles capable to resist high burn-up...
Pacific Northwest Laboratory (PNL) has evaluted, on a laboratory scale, the characteristics and pell...
Nuclear energy continues to play a large role in the energy landscape of the world. Of particular in...
The effects of a powder treatment, the sintering temperature and the sintering time on the grain gro...
The actual tendency all over the world is to manufacture fuel bundles capable to resist high burn-up...
Hydrated gel-microspheres of U, Pu, Th oxide or oxide plus carbon mixture of diameter 400-800µ ...
International audienceU1-xAmxO2±δ mixed-oxides are considered as promising compounds for americium h...
International audienceU$_{1-x}$Am$_x$O$_{2\pm\sigma}$ mixed-oxides are considered as promising compo...
The sol-gel method, which is among the methods used for the production of ThO2-UO2 mixed oxide fuel ...
The External Gelation of Uranium (EGU) process, though originally developed for preparation of fuel ...
Most types of nuclear power reactors use fuel in the form of high density-uranium dioxide pellets cl...
This study is devoted to synthesis and characterization of uranium dioxide microspheres (Ø < 100 μm)...
Globally the most used nuclear fuel material is uranium(IV) oxide (UO2) and it is produced by powder...