Abstract
In reprocessing nuclear fuel it is necessary to remove the clad prior to treating the fuel itself adequately. For stainless-steel cladded fuel, gaseous mixtures of hydrogen fluoride and oxygen at temperatures above 550° C can be used.
Data obtained for non-irradiated stainless-steel Al SI 304 L cladded uranium dioxide pellets are described.
Experiments were performed in a boat reactor and in chemical columns up to 10
cm in diameter for assemblies up to 19 elements 5O cm long. These studies
revealed the main factors for scale-up such as the geometry of the bundle,
the absence or presence of fluidized alumina, the prefluorination of the correct type of alumina and the influence of the self-regulative character of the reaction.
Data obtained for non-irradiated stainless-steel Al SI 304 L cladded uranium dioxide pellets are described.
Experiments were performed in a boat reactor and in chemical columns up to 10
cm in diameter for assemblies up to 19 elements 5O cm long. These studies
revealed the main factors for scale-up such as the geometry of the bundle,
the absence or presence of fluidized alumina, the prefluorination of the correct type of alumina and the influence of the self-regulative character of the reaction.
| Original language | English |
|---|---|
| Publisher | SCK CEN |
| Number of pages | 44 |
| State | Published - Jan 1969 |
Publication series
| Name | SCK CEN Reports |
|---|---|
| Publisher | SCK CEN |
| No. | BLG-435 |