Development and trials of a process for extraction recovery of 99Mo for medical purposes from dissolved irradiated uranium targets

Autor:	A. A. Murzin, Yu. S. Fedorov, N. D. Goletskii, G. Sh. Batorshin, K. V. Bugrov, N. G. Yakovlev, A. A. Naumov, V. S. Ermolin, B. Ya. Zilberman, I. V. Blazheva, N. V. Logunov, A. S. Kudinov, Yu. A. Voroshilov, S. V. Baranov, M. S. Agafonova-Moroz
Rok vydání:	2015
Předmět:	inorganic chemicals Radiochemistry Backwashing chemistry.chemical_element Uranium Enriched uranium complex mixtures Diluent Separation process chemistry.chemical_compound chemistry Nitric acid Physical and Theoretical Chemistry Dissolution Fluoride Nuclear chemistry
Zdroj:	Radiochemistry. 57:292-306
ISSN:	1608-3288 1066-3622
Popis:	A process was developed for extraction recovery of 99Mo from irradiated enriched uranium target. Dissolution of the uranium–aluminum composite in nitric acid in the presence of fluoride ions with the addition of mercury ions, which are subsequently separated by precipitation in the form of iodide, was suggested. Conditions were determined for joint recovery of uranium and molybdenum into the organic phase with 10–15% solutions of HDEHP in a paraffin diluent in the presence of equimolar amounts of TBP, and also for selective backwashing of Mo into a strongly acidic H2O2 solution with the backwash reflux. The efficiency of using a mixture of DTPA with methylamine carbonate for uranium backwashing and solvent regeneration was demonstrated. The recovery and separation process was successfully tested on simulated and real solutions in 20- and 19-step cascades of centrifugal contactors with the feed adjuster without Mo backwash reflux and with its reflux, respectively.
Databáze:	OpenAIRE
Externí odkaz:	https://explore.openaire.eu/search/publication?articleId=doi_________::9cf7746aed116d81fe418f3e52a4a2b0 https://doi.org/10.1134/s1066362215030108 Zobrazit plný text záznamu Full text from SpringerLink