Kinetics of the reaction of UO2, NpO2 and (U, Pu)O2 with fluorine and its chlorine derivatives

P. N. Henrion; A. Leurs

doi:10.1016/0022-3115(71)90195-4

Kinetics of the reaction of UO₂, NpO₂ and (U, Pu)O₂ with fluorine and its chlorine derivatives

P. N. Henrion, A. Leurs

Research output › peer-review

Abstract

Fluorination of oxide fuels has repeatedly been considered as a basis for the reprocessing of spent fuels. In order to test the feasibility of this suggestion, the kinetics of the reactions between F₂, CIF₃ or CIF with various simulated oxide fuel compositions has been investigated by thermogravimetry. The influence on the kinetics of temperature, particle size, porosity, rate of heat removal, etc., was examined, and the work was complemented by chemical analysis, micrography and X-ray diffraction. By means of the fluorine reaction, uranium and plutonium can be separated from non-volatile fission-products, though the separation of uranium and plutonium from each other is incomplete.

Original language	English
Pages (from-to)	1-22
Number of pages	22
Journal	Journal of Nuclear Materials
Volume	41
Issue number	1
DOIs	https://doi.org/10.1016/0022-3115(71)90195-4
State	Published - Oct 1971

ASJC Scopus subject areas

Nuclear and High Energy Physics
General Materials Science
Nuclear Energy and Engineering

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10.1016/0022-3115(71)90195-4

Cite this

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abstract = "Fluorination of oxide fuels has repeatedly been considered as a basis for the reprocessing of spent fuels. In order to test the feasibility of this suggestion, the kinetics of the reactions between F2, CIF3 or CIF with various simulated oxide fuel compositions has been investigated by thermogravimetry. The influence on the kinetics of temperature, particle size, porosity, rate of heat removal, etc., was examined, and the work was complemented by chemical analysis, micrography and X-ray diffraction. By means of the fluorine reaction, uranium and plutonium can be separated from non-volatile fission-products, though the separation of uranium and plutonium from each other is incomplete.",

author = "Henrion, {P. N.} and A. Leurs",

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N2 - Fluorination of oxide fuels has repeatedly been considered as a basis for the reprocessing of spent fuels. In order to test the feasibility of this suggestion, the kinetics of the reactions between F2, CIF3 or CIF with various simulated oxide fuel compositions has been investigated by thermogravimetry. The influence on the kinetics of temperature, particle size, porosity, rate of heat removal, etc., was examined, and the work was complemented by chemical analysis, micrography and X-ray diffraction. By means of the fluorine reaction, uranium and plutonium can be separated from non-volatile fission-products, though the separation of uranium and plutonium from each other is incomplete.

AB - Fluorination of oxide fuels has repeatedly been considered as a basis for the reprocessing of spent fuels. In order to test the feasibility of this suggestion, the kinetics of the reactions between F2, CIF3 or CIF with various simulated oxide fuel compositions has been investigated by thermogravimetry. The influence on the kinetics of temperature, particle size, porosity, rate of heat removal, etc., was examined, and the work was complemented by chemical analysis, micrography and X-ray diffraction. By means of the fluorine reaction, uranium and plutonium can be separated from non-volatile fission-products, though the separation of uranium and plutonium from each other is incomplete.

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