Synthesis and investigation of uranyl molybdate UO2MoO4

In order to examine easily synthetic conditions of uranyl molybdate, UO2MoO4, used for the reprocessing process study of spent nuclear oxide fuels in alkaline molybdate melts, the uranium molybdate compounds were produced from U3O8 powder and anhydrous MoO3 reagent. The results of having investigate...

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Bibliographic Details
Published in:Journal of nuclear materials 2013-02, Vol.433 (1-3), p.397-403
Main Authors: Nagai, Takayuki, Sato, Nobuaki, Kitawaki, Shin-ichi, Uehara, Akihiro, Fujii, Toshiyuki, Yamana, Hajimu, Myochin, Munetaka
Format: Article
Language:English
Subjects:
Applied sciences
Controled nuclear fusion plants
Diffraction
Dissolution
Energy
Energy. Thermal use of fuels
Exact sciences and technology
Fission nuclear power plants
Fuels
Heating
Installations for energy generation and conversion: thermal and electrical energy
Melts
Molybdates
Nuclear fuels
Oxides
Preparation and processing of nuclear fuels
Reprocessing
Uranium
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Summary:In order to examine easily synthetic conditions of uranyl molybdate, UO2MoO4, used for the reprocessing process study of spent nuclear oxide fuels in alkaline molybdate melts, the uranium molybdate compounds were produced from U3O8 powder and anhydrous MoO3 reagent. The results of having investigated them in solid state by using X-ray diffractometry and Raman spectrometry, it was confirmed that UO2MoO4 could be synthesized by heating mixed powder of U3O8 and MoO3 with stoichiometric mole ratio at 770°C for 4h under air atmosphere. Moreover, adding this UO2MoO4 into Li2MoO4Na2MoO4 eutectic melt, most of the dissolved uranium species in the melt were observed as hexa–valent uranyl ions by absorption spectrophotometry.
ISSN:0022-3115
1873-4820
DOI:10.1016/j.jnucmat.2012.10.010