Journal of Nuclear and Radiochemical Sciences
Online ISSN : 1883-5813
Print ISSN : 1345-4749
ISSN-L : 1345-4749
Technetium Separation for Future Reprocessing
T. AsakuraS. HotokuY. BanM. MatsumuraY. Morita
著者情報
ジャーナル フリー

2005 年 6 巻 3 号 p. 271-274

詳細
抄録
Tc extraction and separation experiments were performed basing on PUREX technique with using spent UO2 fuel with burn-up of 44 GWd t-1. The experimental results were examined with performing calculations by a simulation code ESSCAR (Extraction System Simulation Code for Advanced Reprocessing). It was demonstrated that Tc can be extracted almost quantitatively from a dissolver solution and that extracted Tc also can be recovered almost quantitatively by scrubbing. Further, it is clearly presented with the calculation results of ESSCAR that Tc extraction mechanism is dominated by the synergistic effect of Zr and U.
著者関連情報
© The Japan Society of Nuclear and Radiochemical Sciences
前の記事 次の記事
feedback
Top