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Synthesis and investigation of uranyl molybdate UO$$_{2}$$MoO$$_{4}$$

Nagai, Takayuki  ; Sato, Nobuaki*; Kitawaki, Shinichi ; Uehara, Akihiro*; Fujii, Toshiyuki*; Yamana, Hajimu*; Myochin, Munetaka

In order to examine easily synthetic conditions of uranyl molybdate, UO$$_{2}$$MoO$$_{4}$$, used for the reprocessing process study of spent nuclear oxide fuels in alkaline molybdate melts, the uranium molybdate compounds were produced from U$$_{3}$$O$$_{8}$$ powder and anhydrous MoO$$_{3}$$ reagent. The results of having investigated them in solid state by using X-ray diffractometry and Raman spectrometry, it was confirmed that UO$$_{2}$$MoO$$_{4}$$ could be synthesized by heating mixed powder of U$$_{3}$$O$$_{8}$$ and MoO$$_{3}$$ with stoichiometric mole ratio at 770$$^{circ}$$C for 4 h under air atmosphere. Moreover, adding this UO$$_{2}$$MoO$$_{4}$$ into Li$$_{2}$$MoO$$_{4}$$-Na$$_{2}$$MoO$$_{4}$$ eutectic melt, most of the dissolved uranium species in the melt were observed as hexa-valent uranyl ions by absorption spectrophotometry.

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Category:Materials Science, Multidisciplinary

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