[article]
Titre : |
99Mo separation from high-concentration irradiated uranium nitrate and uranium sulfate solutions |
Type de document : |
texte imprimé |
Auteurs : |
Gregory E. Dale, Auteur ; Dale A. Dalmas, Auteur ; Michael J. Gallegos, Auteur |
Année de publication : |
2012 |
Article en page(s) : |
pp. 13319-13322 |
Note générale : |
Industrial chemistry |
Langues : |
Anglais (eng) |
Mots-clés : |
Uranium Sulfate |
Résumé : |
We report separation data indicating that 99Mo can be separated from a vast excess of either uranyl sulfate or uranyl nitrate in irradiated dilute acid solutions. These results suggest that, if medical isotope 99Mo is produced during fission of high concentrations of low enriched uranium sulfate solution fuel, it is feasible to both recover >90% of the 99Mo for further purification and the uranium for recycle. |
ISSN : |
0888-5885 |
En ligne : |
http://pubs.acs.org/doi/abs/10.1021/ie3008743 |
in Industrial & engineering chemistry research > Vol. 51 N° 40 (Octobre 2012) . - pp. 13319-13322
[article] 99Mo separation from high-concentration irradiated uranium nitrate and uranium sulfate solutions [texte imprimé] / Gregory E. Dale, Auteur ; Dale A. Dalmas, Auteur ; Michael J. Gallegos, Auteur . - 2012 . - pp. 13319-13322. Industrial chemistry Langues : Anglais ( eng) in Industrial & engineering chemistry research > Vol. 51 N° 40 (Octobre 2012) . - pp. 13319-13322
Mots-clés : |
Uranium Sulfate |
Résumé : |
We report separation data indicating that 99Mo can be separated from a vast excess of either uranyl sulfate or uranyl nitrate in irradiated dilute acid solutions. These results suggest that, if medical isotope 99Mo is produced during fission of high concentrations of low enriched uranium sulfate solution fuel, it is feasible to both recover >90% of the 99Mo for further purification and the uranium for recycle. |
ISSN : |
0888-5885 |
En ligne : |
http://pubs.acs.org/doi/abs/10.1021/ie3008743 |
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