[1E15-19] Vitrification 3

[1E19] Basic Research Programs of Vitrification Technology for Waste Volume Reduction

(125) Extraction Behavior of Neptunium in Solvent Extraction Process

*Masaumi Nakahara¹, Takehiko Sato¹, Yuichi Sano¹ (1. JAEA)

Keywords:Chemical Processing Facility, Centrifugal contactor, Solvent extraction method, Tri-n-butyl phosphate, Neptunium

The recovery of Np with U and Pu have been proposed using tri-n-butyl phosphate as an extractant in the solvent extraction process. A hot experiment was carried out with the flowsheet to confirm extraction behavior of Np and decontamination performance of fission products. A dissolver solution derived from irradiated nuclear fuel was used as feed solution in the experiment at the Chemical Processing Facility. The experimental results will be reported in our presentation.