Choice of the Optimum Composition of the Solution Fuel for a Homogeneous Reactor and of Termoxid Sorbent for Recovering 99Mo
- Авторлар: Denisov E.1, Betenekov N.1
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Мекемелер:
- Yeltsin Ural Federal University
- Шығарылым: Том 60, № 5 (2018)
- Беттер: 541-547
- Бөлім: Article
- URL: https://journals.rcsi.science/1066-3622/article/view/224720
- DOI: https://doi.org/10.1134/S1066362218050119
- ID: 224720
Дәйексөз келтіру
Аннотация
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).
Авторлар туралы
E. Denisov
Yeltsin Ural Federal University
Хат алмасуға жауапты Автор.
Email: eidenisov@urfu.ru
Ресей, ul. Mira 19, Yekaterinburg, 620002
N. Betenekov
Yeltsin Ural Federal University
Email: eidenisov@urfu.ru
Ресей, ul. Mira 19, Yekaterinburg, 620002