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


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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).

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E. Denisov

Yeltsin Ural Federal University

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Email: eidenisov@urfu.ru
俄罗斯联邦, ul. Mira 19, Yekaterinburg, 620002

N. Betenekov

Yeltsin Ural Federal University

Email: eidenisov@urfu.ru
俄罗斯联邦, ul. Mira 19, Yekaterinburg, 620002

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