Dissolution of morphology-controlled Th1-xUxO2 model dioxides
Creators
- 1. Groupe de Radiochimie, IPNO, UMR 8608 CNRS / Univ. Paris-Sus-11, Bat. 100, 91406 Orsay (France)
- 2. ICSM, UMR 5257 CEA / CNRS / UM2 / ENSCM, 30207 Bagnols / Ceze (France)
Description
The influence of the morphology of Th1-xUxO2 solid solutions on their chemical durability was evaluated considering two routes of preparation, involving either direct precipitation of a precursor or hydrothermal conditions. The great differences in terms of morphology and crystallization state of the so-obtained samples were correlated to an important variation of the specific surface area of the final dioxides then to the density of the sintered pellets fired at 1500 deg. C. In order to evaluate the chemical durability of such materials, leaching tests were undertaken. The dissolution of the samples was associated to low normalized dissolution rates typically ranging from 3.10-6 g.m-2.day-1 (HNO3 10-4 M) to 2 10-5 g.m-2.day-1 (HNO3 10-1 M) at 25 deg. C for x equals 0.25. The influence of the x value on the normalized dissolution rate was found to be limited due to the homogenization of the cationic distribution obtained through the precipitation process. Moreover, the good crystallization state initially obtained from hydrothermal conditions led to a higher chemical durability. (authors)
Availability note (English)
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Additional details
Publishing Information
- Imprint Pagination
- 8 p.
- Report number
- INIS-FR--09-0090
Conference
- Title
- Nuclear fuel cycle for a sustainable future
- Acronym
- Atalante 2008
- Dates
- 19-23 May 2008
- Place
- Montpellier (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 40034681
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FUEL PELLETS; LEACHING; MICROSTRUCTURE; MIXED OXIDE FUELS; SINTERING; THORIUM OXIDES; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; DISSOLUTION; ENERGY SOURCES; FABRICATION; FUELS; MATERIALS; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; PELLETS; REACTOR MATERIALS; SEPARATION PROCESSES; SOLID FUELS; THORIUM COMPOUNDS; URANIUM COMPOUNDS; URANIUM OXIDES
Optional Information
- Notes
- 14 refs.