Decontamination Study of Some Noticeable Fission Products in the Actinides Recovery by Truex Process

نویسندگان

  • Toshiyuki Fujii
  • Hajimu Yamana
  • Hirotake Moriyama
چکیده

Decontamination performance of some noticeable fission products from TRU elements by the TRUEX process was calculated with a multistage extraction simulation code. The batch extraction data of molybdenum, palladium, antimony, and cerium, which have been obtained in our related TRUEX studies, were provided for the calculation. For uranium, plutonium, and americium, literature data were used. A mixed solvent of 0.2 M OφD[IB]CMPO and 1.0 M TBP in n-dodecane was employed as the TRUEX solvent. The feed and scrub solutions were nitric acid solutions, and the distribution of nitric acid between the organic and aqueous phases was calculated by modified SEPHIS code. The change in the decontamination performance by adding oxalic acid was also evaluated.

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تاریخ انتشار 2001