Extraction Technology for Reprocessing U–Be Fuel Solutions.

Autor: Volk, V. I., Arseenkov, L. V., Safiulina, A. M., Dvoeglazov, K. N., Zverev, D. V., Logunov, M. V., Ermolin, V. S.
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Zdroj: Radiochemistry; Jun2022, Vol. 64 Issue 3, p344-348, 5p
Abstrakt: The results of experiments are presented on testing the separation of uranium from U-Be nuclear fuel solutions by extraction. It was shown that the degree of uranium extraction using a solution of 10 vol% TBP in RED-3 from a nitric acid solution of this fuel is 98.7%. Transfer of uranium into the re-extract is 97.9%. More than 99.99 % of beryllium goes into the extraction raffinate intended for further vitrification. The results of the study were used for the preparation of technological regulations on reprocessing of U-Be SNF at the RT-1 plant of the Mayak Production Association. The industrial-scale reprocessing of this fuel confirmed the values determined in the study. [ABSTRACT FROM AUTHOR]
Databáze: Complementary Index