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Radiochemistry

, Volume 60, Issue 5, pp 541–547 | Cite as

Choice of the Optimum Composition of the Solution Fuel for a Homogeneous Reactor and of Termoxid Sorbent for Recovering 99Mo

  • E. I. DenisovEmail author
  • N. D. Betenekov
Article
  • 7 Downloads

Abstract

T-52 sorbent was chosen for recovering 99Mo from low-enriched uranium fuel of a homogeneous solution reactor, because this sorbent exhibits the maximal 99Mo distribution coefficient in sorption from solutions containing 150–360 g L–1 uranium. The use of sulfate and nitrate solutions for producing and recovering 99Mo from the fuel of a homogeneous solution reactor was compared. The optimum composition of the solution fuel of a commercial reactor for 99Mo production was suggested: nitric acid uranium solution (20% 235U, 100–200 g L–1, 1 M HNO3).

Keywords

molybdenum-99 uranium homogeneous solution reactor low-enriched uranium fuel sulfate and nitrate solutions sorption Termoxid T-5 Termoxid T-52 distribution coefficient 

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Copyright information

© Pleiades Publishing, Inc. 2018

Authors and Affiliations

  1. 1.Yeltsin Ural Federal UniversityYekaterinburgRussia

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