2023 Fall Meeting

Presentation information

Oral presentation

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

[1E15-19] Vitrification 3

Wed. Sep 6, 2023 4:45 PM - 6:00 PM Room E (Okuma Machine Tool Eng. Bildg. 1F Okuma Hall)

Chair:Satoshi Okada(HGNE)

5:45 PM - 6:00 PM

[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.

Abstract password authentication.
Password is required to view the abstract. Please enter a password to authenticate.

Password