[1E01-03] Sorption Separation 1

[1E01] Creation of Porous Polysiloxane Sponge Enabling Catch and Release of Uranium

*Atsuro Furuichi¹, Naokazu Idota², Takehiko Tsukahara^1,2 (1. TokyoTech, School of Mater. Chem. Technol, 2. TokyoTech, Zero-Carbon Energy)

Keywords:Disposal of radioactive waste, Uranium separation, PDMS sponge, Graphene

In the decommissioning of Fukushima Daiichi Nuclear Power Plant, a new decontamination technology that can easily and efficiently detach and recover U/Pu from concrete material is needed. In this study, GO-PDMS sponges were prepared by encapsulating graphene oxide (GO) with U-selective functional groups in porous polydimethylsiloxane (PDMS) sponge, and their U adsorption performance was evaluated. PDMS sponge was prepared by calcination of a solution containing monomer, curing agent, and citric acid, followed by immersion in ethanol. GO-Im, in which imidazole (Im) was immobilized on GO, was introduced into the sponge to form GO-Im/PDMS sponge. As a result of adsorption test, GO-Im/PDMS sponge and GO-Im powder showed high U adsorption performance. The applicability to decontamination of U waste was also discussed.