New methods for co-conversion of uranium (IV) and plutonium (IV) in aqueous medium to prepare mixed oxide (U, Pu)O2 for MOX fuels
Description
At the present time, the uranium-plutonium mixed oxide fuel is synthesized by mechanical mixtures and powder sintering of UO2 and PuO2. This work deals with the study of a new way: synthesis of mixed oxides by aqueous way allowing to make an intimate mixture of uranium and plutonium. The (U, Pu) co-conversion consists to precipitate U(IV) and Pu(IV) ions in homologous compounds. The U(IV) and Pu(IV) keeping in nitric acid requires to add a selective actinides (IV) chelating agent, in order to avoid the Pu(IV) reduction by U(IV). The method used is based on the complex formation with CHON (carbon (C), hydrogen (H), oxygen (O) and nitrogen (N)) ligands. These molecules can be potentially incinerated. Two ligands have been studied: the diethylene-tri-amino-penta-acetic acid (DTPA) and the oxalate ions. The thermodynamic and kinetic stability of the U(IV)-DTPA and Pu(IV)-DTPA, has been revealed; the second system has shown the possibility of co-precipitation of the trioxalato actinides (IV) complexes, after having verified the kinetic stability of this solution. The co-precipitates have been obtained at different amounts of Pu and present a complete homogeneity. Their formula is M2(UxPu1-x)(C2O4)3, 6-7 H2O (with M=alkaline ions, ammonium). The calcination of the formed co-precipitates, has allowed to obtain homogeneous mixed oxides (U, Pu)O2. This result depends on the analysis of the X rays diffraction diagram of the mixed oxides and of their capacity to be dissolved in nitric acid 6 mol.l-1. The study of these two systems has been theoretically transposed to others CHON (DOTA) molecules. This way opens a lot of potentialities for the preparation as well as MOX fuels than new fuels or for the preparation of targets for actinides nuclear incineration. (O.M.)
Availability note (English)
Also available from Bibliothrque Universitaire de Sciences, Domaine universitaire Batiment 407, 91405 - Orsay Cedex, FranceFiles
52002204.pdf
Files
(37.6 MB)
| Name | Size | Download all |
|---|---|---|
|
md5:378515580c46c697737967325c550900
|
37.6 MB | Preview Download |
Additional details
Additional titles
- Original title (French)
- Nouvelles methodes de co-conversion par voie aqueuse de l'uranium (IV) et du plutonium (IV) pour preparer des oxydes mixtes (U, Pu)O2 en vue de la fabrication de combustibles MOX
Publishing Information
- Imprint Pagination
- 246 p.
- Report number
- FRNC-TH--7175
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 52002204
- Subject category
- S37: INORGANIC, ORGANIC, PHYSICAL AND ANALYTICAL CHEMISTRY; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Thesis
- Descriptors DEI
- CALCINATION; CHEMICAL REACTION KINETICS; CHEMICAL STATE; COPRECIPITATION; CRYSTALLIZATION; DIFFERENTIAL THERMAL ANALYSIS; HYDROLYSIS; NUCLEAR FUELS; OXALATES; PLUTONIUM COMPLEXES; REDOX REACTIONS; RESEARCH PROGRAMS; SOLUBILITY; STOICHIOMETRY; THERMAL GRAVIMETRIC ANALYSIS; THERMODYNAMICS; URANIUM COMPLEXES; X-RAY DIFFRACTION
- Descriptors DEC
- ACTINIDE COMPLEXES; CARBOXYLIC ACID SALTS; CHEMICAL ANALYSIS; CHEMICAL REACTIONS; COHERENT SCATTERING; COMPLEXES; DECOMPOSITION; DIFFRACTION; ENERGY SOURCES; FUELS; GRAVIMETRIC ANALYSIS; KINETICS; LYSIS; MATERIALS; PHASE TRANSFORMATIONS; PRECIPITATION; PYROLYSIS; QUANTITATIVE CHEMICAL ANALYSIS; REACTION KINETICS; REACTOR MATERIALS; SCATTERING; SEPARATION PROCESSES; SOLVOLYSIS; THERMAL ANALYSIS; THERMOCHEMICAL PROCESSES; TRANSURANIUM COMPLEXES
Optional Information
- Notes
- 155 refs.; Available from the INIS Liaison Officer for France, see the INIS website for current contact and E-mail addresses; This record replaces 38115116