Author/Authors :
Nagai، نويسنده , , Takayuki and Sato، نويسنده , , Nobuaki and Kitawaki، نويسنده , , Shin-ichi and Uehara، نويسنده , , Akihiro and Fujii، نويسنده , , Toshiyuki and Yamana، نويسنده , , Hajimu and Myochin، نويسنده , , Munetaka، نويسنده ,
Abstract :
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 4 h 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.
