Presentation Information

10:50 AM - 11:05 AM JST(1:50 AM - 2:05 AM UTC)

[1A06]Investigation of chemical state of uranium in simulated waste glass coexisting zirconium molybdate

*YUSUKE AOYAMA¹, NANAKO KATSUOKA¹, TAKAYUKI NAGAI¹, YOSHIHIRO OKAMOTO¹, DAISUKE AKIYAMA², AKIRA KIRISHIMA² (1. JAEA, 2. Tohoku Univ.)

Keywords:

Reprocessing plant,High-level radioactive liquid waste,Vitrification,Borosilicate glass,X-ray absorption fine structure,Zirconium molybdate,Uranium

When spent nuclear fuel is reprocessed, uranium and plutonium are recovered. High-level radioactive waste (HALW) generated during reprocessing is solidified by melting it with high-temperature borosilicate glass, resulting in vitrified radioactive waste. Uranium that can be transferred from the process into HALW can exist in a wide variety of chemical forms. Therefore, we are investigating the chemical state of uranium in borosilicate glasses under various conditions to assess the influence of other elements present. This report presents the results of XAFS measurements and analyses on uranium-containing glasses that incorporate zirconium molybdate, to determine the chemical state of uranium in simulated waste glass containing a large amount of undissolved residue.

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