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

Autor:	E. I. Denisov, N. D. Betenekov
Rok vydání:	2018
Předmět:	Partition coefficient chemistry.chemical_compound Sorbent Nitrate chemistry Chemical engineering Nitric acid Homogeneous chemistry.chemical_element Sorption Physical and Theoretical Chemistry Sulfate Uranium
Zdroj:	Radiochemistry. 60:541-547
ISSN:	1608-3288 1066-3622
DOI:	10.1134/s1066362218050119
Popis:	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).
Databáze:	OpenAIRE
Externí odkaz:	https://explore.openaire.eu/search/publication?articleId=doi_________::f9bd2ffa93fb994bd5d0ee7d2bc7686e https://doi.org/10.1134/s1066362218050119 Zobrazit plný text záznamu Full text from SpringerLink