2022 Fall Meeting

Presentation information

Oral presentation

V. Nuclear Fuel Cycle and Nuclear Materials » 505-1  Radioactive Waste Management

[1A06-08] Nuclide Adsorption and Separation 1

Wed. Sep 7, 2022 2:45 PM - 3:35 PM Room A (E1 Bildg.1F No.10)

Chair:Daisuke Sugiyama(CRIEPI)

3:00 PM - 3:15 PM

[1A07] Uranium recovery from the solution originated sludge waste

(2) Comparison study of uranyl nitrate separation methods by monoamide extractant

*Madoka Saito1, Youko Takahatake1, Sou Watanabe1, Masayuki Watanabe1, Takehiko Tsukahara2, Atsuki Naruse2 (1. JAEA, 2. Tokyo Tech)

Keywords:Uranium recovery, monoamide extractant, gelling extraction method, solvent extraction method, extraction chromatography method

The sludge contained uranium generated production of nuclear fuel has been storage. The sludge is immersed in some kinds of solution. After immersion, uranium is recovered from the solution. Solvent extraction method, extraction chromatography and gelling extraction method were conducted on uranyl nitrate solution using monoamide extractant to compare on amount of waste and running cost on each methods. The gelling extraction method was superior to other two methods.