Analytical study of the aqueous corrosion of uranium dioxide by physico-chemical methods
Description
Sintered uranium dioxide pellets have undergone static leaching tests carried out between 25 and 90°C between 1 day and 12 months. The main aim of this study was to characterize the possible alterations of the UO2 surface after an aqueous corrosion treatment, by the mean of the Rutherford backscattering spectroscopy, of the scanning electron microscopy and of the photoelectron spectrometry and to measure the release of uranium in solution. The results differ a lot according to the kind of the used leachate (deionized water or Volvic mineral water). The measurements of the uranium concentration in the leachates carried out by laser spectro-fluorimetry show that the release rate of this element increases with temperature in the deionized water and decreases in Volvic water. This last phenomenon is probably due to the formation of an alteration layer rich in magnesium silicate revealed at the surface of the leached samples in 90°C. At this temperature, the first steps of the aqueous corrosion are characterized by a constant U(IV)/U(VI) ratio. The leaching in deionized water brings no perceptible alteration at the surface state and proves that there is in this case a congruent dissolution. (O.M.)
Availability note (English)
Also available from: Bibliotheque Universitaire de Paris 11. Centre scientifique dOrsay, Batiment, 407, 91405 - Orsay Cedex (France)Abstract (French)
Des Dastilles de dioxyde d'uranium fritte ont ete soumises a des tests de lixiviation statique menes entre 25 et 90°C de 1 jour a 12 mois. L'objectif principal de cette etude visait a caracteriser les eventuelles modifications de la surface de UO2 apres traitement de corrosion aoueuse au moyen de la retrodiffusion eiastioue Rutherford, de la microscopie electronique a balayage, de la spectrometrie de photoelectrons et a mesurer le relachement d'uranium en solution. Les resultats different fortement en fonction de la nature du lixiviant utilise (eau deionisee et eau minerale de Volvic). Les mesures de la concentation en uranium dans les lixiviats effectuees oar soectrofluorimetrie laser montrent aue le taux de relachement de cet element croit avec la temperature en eau deionisee alors ou'il decroit en eau de Volvic. Ce dernier phenomene est orobaoiement du a la formation d'une couche q'alteration riche en silicate de magnesium mise en evidence a la surface des echantillons lixivies a 90°C. A cette temperature, les premiers stades de la corrosion aoueuse sont caracterises car un rapport U(IV) / U (VI) constant. La lixiviation en eau deionisee n'apporte pas de modification perceptible de l'etat de surface ce oui temoigne d'une dissolution congruente. (auteur)Files
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Additional details
Additional titles
- Original title (French)
- Etude de la corrosion aqueuse du dioxyde d'uranium au moyen de techniques physico-chimiques d'analyse
Publishing Information
- Imprint Pagination
- 165 p.
- Report number
- FRCEA-TH--16306
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 54064499
- Subject category
- S36: MATERIALS SCIENCE; S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Thesis
- Descriptors DEI
- CORROSION; LEACHING; MICROANALYSIS; MORPHOLOGY; PHOTOELECTRON SPECTROSCOPY; RADIOACTIVE WASTE DISPOSAL; RESEARCH PROGRAMS; RUTHERFORD BACKSCATTERING SPECTROSCOPY; SCANNING ELECTRON MICROSCOPY; SINTERING; URANIUM DIOXIDE; VALENCE
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; CHEMICAL REACTIONS; DISSOLUTION; ELECTRON MICROSCOPY; ELECTRON SPECTROSCOPY; FABRICATION; MANAGEMENT; MICROSCOPY; OXIDES; OXYGEN COMPOUNDS; RADIOACTIVE WASTE MANAGEMENT; SEPARATION PROCESSES; SPECTROSCOPY; URANIUM COMPOUNDS; URANIUM OXIDES; WASTE DISPOSAL; WASTE MANAGEMENT
Optional Information
- Notes
- 116 refs.; Available from the INIS Liaison Officer for France, see the INIS website for current contact and E-mail addresses; This record replaces 37115501