화학공학소재연구정보센터
학회 한국화학공학회
학술대회 2005년 가을 (10/21 ~ 10/22, 인하대학교)
권호 11권 2호, p.1966
발표분야 분리기술
제목 Mass Transfer Characteristics of Oxygen Ions Released from Uranium Oxide to a Molten Salt
초록 The volume and the radioactivity of spent oxide fuels discharged from commercial PWRs are reduced by a quarter when the oxygens of the irradiated uranium oxides are removed and some of the fission products are separated from the reduced metals. Recently, pyroprocess using a molten salt has been considered as a promising and economical option for treating spent fuels. Korea Atomic Energy Research Institute (KAERI) has developed a molten LiCl-based process which adopts an electrolytic reduction technology. An inert ceramic membrane filled with U3O8 powders acts as a cathode where the oxygens are ionized and, at the opposite side of an electrolytic cell, platinum anodes take the electrons from the oxygen ions to change them into gas. The mass transfer of the oxygen ions is of great interest for the sake of analysing the process. The mass transfer could be divided into three steps; 1) internal diffusion from the inside of a metal oxide powder to the surface, 2) external diffusion along the outside of the metal powers, and 3) mass transfer through the fine pores of the ceramic membrane. The mass transfer is investigated by an electrochemical and a simple chemical method to conclude that the internal diffusion is the rate-determining step.
저자 박병흥, 서중석, 정기정, 박성원
소속 한국원자력(연)
키워드 uranium oxide; molten salt; oxygen ion; mass transfer
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