Authors:Kwang-Wook Kim, Kee-Chan Song, Eil-Hee Lee, and Jae-Hyng Yoo
A new static contactor was developed for solvent extraction using capillary phenomena induced among clearances formed within
a highly packed fiber bundle. Feeding two immiscible phases cocurrently into the fiber bundle generated a very large liquid-liquid
contact area for mass transfer within the fiber bundle without any flow turbulence or drop phenomena. In order to test the
characteristics and stability of the fiber bundle contactor, continuous extraction experiments were carried out using the
fiber bundle contactor with a TBP-uranyl ion-nitric acid system. The fiber bundle contactor had the same extraction performance
as that of an ideal batch extractor with good reproducibility due to the sufficient liquidliquid contact area generated by
the packed fiber bundle. A minimum residence time of the aqueous phase within the fiber bundle contactor was required for
the extraction system to reach an extraction equilibrium state. In the TBP-uranyl ion-nitric acid system, the residence time
was about 1.9 minutes. This contactor was confirmed to be effective enough to perform solvent extraction and to study the
extraction kinetics because of the stable and large static liquid-liquid contact area.
Authors:Kwang-Wook Kim, Soo-Ho Kim, Kee-Chan Song, Eil-Hee Lee, and Jae-Hyung Yoo
In order to remove U, Tc, and Np, which are positioning materials or target nuclides for transmutation, from the high-level radioactive waste, conditions of co-extraction and sequential stripping of the nuclides were studied by using 30 vol.% TBP. On the basis of the experiments performed on each element of U, Tc, and Np, a combination of co-extraction of U, Tc, Np Tc stripping Np stripping U stripping was suggested. To enhance the Np extraction yield, the electrolytic oxidation of Np(V) was required at the co-extraction step. For the stripping of Tc 5M HNO3, of Np the electrolytic reduction of Np(VI) to Np(V), and of U 0.3M sodium carbonate were used. Phase ratios (O/A or A/O) were recommended to be of 2-3, for co-extraction and for stripping.
Authors:Kwang-Wook Kim, Kee-Chan Song, Eil-Hee Lee, In-Kyu Choi, and Jae-Hyung Yoo
The change of Np oxidation state in nitric acid and the effect of nitrous acid on the oxidation state were analyzed by spectrophotometry, solvent extraction, and electrochemical methods. The Np extraction with 30 vol.% TBP was enhanced by the adjustment of the Np oxidation state using a glassy carbon fiber column electrode system. The knowledge of electrolytic behavior of nitric acid was important because the nitrous acid affecting the Np redox reaction was generated during the adjustment of the Np oxidation state. The Np solution used in this work consisted of Np(V) and Np(VI) but no Np(IV). The ratio of Np(V) in the range of 0.5M5.5 M nitric acid was 32%19%. The electrolytic oxidation of Np(V) to Np(VI) in the solution enhanced the Np extraction efficiency about five times higher than without electrolytic oxidation. It was confirmed that the nitrous acid in a concentration of less than about 10–5 M acted as a catalyst to accelerate the chemical oxidation reaction of Np(V) to Np(VI).
Authors:Kwang-Wook Kim, Jae-Won Lee, Dong-Young Chung, Eil-Hee Lee, Kweon-Ho Kang, Kune-Woo Lee, Kee-Chan Song, Myung-June Yoo, Geun-Il Park, and Jei-Kwon Moon
This work studied a way to reclaim uranium from contaminated UO2 oxide scraps as a sinterable UO2 powder for UO2 fuel pellet fabrication, which included a dissolution of the uranium oxide scraps in a carbonate solution with hydrogen peroxide
and a UO4 precipitation step. Dissolution characteristics of reduced and oxidized uranium oxides were evaluated in a carbonate solution
with hydrogen peroxide, and the UO4 precipitation were confirmed by acidification of uranyl peroxo–carbonate complex solution. An agglomerated UO4 powder obtained by the dissolution and precipitation of uranium in the carbonate solution could not be pulverized into fine
UO2 powder by the OREOX process, because of submicron-sized individual UO4 particles forming the agglomerated UO4 precipitate. The UO2 powder prepared from the UO4 precipitate could meet the UO2 powder specifications for UO2 fuel pellet fabrication by a series of steps such as dehydration of UO4 precipitate, reduction, and milling. The sinterability of the reclaimed UO2 powder for fuel pellet fabrication was improved by adding virgin UO2 powder in the reclaimed UO2 powder. A process to reclaim the contaminated uranium scraps as UO2 fuel powder using a carbonate solution was finally suggested.