U-235 enrichment by chemical exchange in the U4+-UO22+ system, by using ion exchange resins

Citation
R. Horga et al., U-235 enrichment by chemical exchange in the U4+-UO22+ system, by using ion exchange resins, REV CHIM, 52(7-8), 2001, pp. 377-381
Citations number
8
Categorie Soggetti
Chemical Engineering
Journal title
REVISTA DE CHIMIE
ISSN journal
00347752 → ACNP
Volume
52
Issue
7-8
Year of publication
2001
Pages
377 - 381
Database
ISI
SICI code
0034-7752(200107/08)52:7-8<377:UEBCEI>2.0.ZU;2-R
Abstract
The experimental data on U-235 enrichment by isotopic exchange U-235/U-238 in U4+-UO22+ system on cation exchange resin C-100 (produced by Purolite) a nd in the system U4+-[UO2Clx](2-x), on anion exchange resin Dowex-1 (Sigma) are presented. In both cases a thermostated glass column was utilised. Cat ion exchange resin was passed in R-Ti3+ form, then the column was feeded wi th 0.047M UO2Cl2 solution. According to the isotopic exchange between U4+ f ixed on resin and UO22+ from solution U-235 is enriched in the solution pha se at the front of U band, and U-238 in the resin phase at the rear of uran ium band. The uranium solution which has passed through the column was frac tioned, by means of an automatic sample colector, in 100 small fractions. F or each,sample fraction uranium content, and uranium isotopic ratio U-235/U -238 were determined. In the case of Dowex-1 the resin was converted in R-C l form with 5M HCl solution, then 0.1 M UO2Cl2 solution in 5M HCl was feede d in the column, and on the resin were fixed the following complex anions: [UO2Cl3](-), [UO2Cl4](2-). When all resin was passed in R-U(IV) form, the c olumn was feeded with 0.1 M TiCl3 solution in 5 M HCl. According to the iso topic exchange between [UO2Clx](2-x) fixed on resin and U4+ from solution U -235 will be enriched in the resin phase, at the rear edge of uranium band. The effluent from the bottom of the column was collected in small fraction s on which uranium content and isotopic ratio U-235/U-238 were determined. All isotopic analysis were performed on SMIT-1 thermoionization mass spectr ometer. In both cases presented here, U-235 enrichments were experimentally determined. Temperature increase with 10 degreesC had not a significant ef fect on U-235 enrichment in U4+-UO22+ exchange system on cation exchange re sin C-100. The 235U enrichment was diminished when feed flow rate of the co lumn with Dowex-1 increased two times. The eluent volume, corresponding to the uranium U-235 maximum enrichment was 1428 mL on cation exchange resin, and 692 mL on anion exchange resin.