SEPARATION OF FISSION PRODUCTS, NITRIC ACID, PLUTONIUM AND URANIUM BY EXTRACTION CHROMATOGRAPHY WITH TBP - POLYSTYRENE
Two types of simulated fuel solutions have been tested. The first contained uranium and simulated fission products corresponding to a burn-up of 3.3 %. The transplutonium elements Am and Cm were simulated by the homologous lanthanides Eu and Gd. In the other solution 18 % of the uranium was replaced by plutonium. The operation sequence of a system with two columns, each of a volume of 2 1, was as follows: 200 ml of the solution (50 g U or U + Pu, 4M HNO-3) were fed onto a first column to extract uranium and plutonium. The bulk of the fission products and the higher simulated actinides were washed with 6M HNO-3 onto a second column. Both columns were then eluted with distilled water. Uranium and the fission product fractions were detected by photometry. Additionally, for the fission products Gd, Eu, Ru, Sr, Cs, Zr and Nb, tracers were added for their determination by gamma spectroscopy. The plutonium was measured by alpha- spectroscopy and nitric acid by titration. It was shown possible to separate on TBP impregnated polystyrene columns fission products and transplutonium elements from uranium, plutonium and from HNO-3.
Bibliographic Reference: 1ST INTERNATIONAL CONFERENCE ON THE CHEMISTRY AND TECHNOLOGY OF THE LANTHANIDES AND ACTINIDES, VENEZIA (ITALY), SEPT. 5-10, 1983 - WRITE TO CEC LUXEMBOURG, DG XIII/A2, POB 1907 MENTIONING PAPER E 31202 ORA.
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Record Number: 1989122038000 / Last updated on: 1987-01-01
Available languages: en