Synthesis and investigation of uranyl molybdate UO2MoO 4

Takayuki Nagai, Nobuaki Sato, Shin Ichi Kitawaki, Akihiro Uehara, Toshiyuki Fujii, Hajimu Yamana, Munetaka Myochin

研究成果: Article査読

7 被引用数 (Scopus)

抄録

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 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 2MoO4 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 UO 2MoO4 into Li2MoO4Na 2MoO4 eutectic melt, most of the dissolved uranium species in the melt were observed as hexa-valent uranyl ions by absorption spectrophotometry.

本文言語English
ページ(範囲)397-403
ページ数7
ジャーナルJournal of Nuclear Materials
433
1-3
DOI
出版ステータスPublished - 2013

ASJC Scopus subject areas

  • 核物理学および高エネルギー物理学
  • 材料科学(全般)
  • 原子力エネルギーおよび原子力工学

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