BEHAVIOR OF TRITIUM IN THE PUREX PROCESS

Gunzo UCHIYAMA Department of Fuel Cycle Safety Research, Japan Atomic Energy Research Institute(JAERI), Tokai-mura, Naka-gun, Ibaraki-ken, 319-11, Japan

Sachio FUJINE Department of Fuel Cycle Safety Research, Japan Atomic Energy Research Institute(JAERI), Tokai-mura, Naka-gun, Ibaraki-ken, 319-11, Japan

Mitsuru MAEDA Department of Fuel Cycle Safety Research, Japan Atomic Energy Research Institute(JAERI), Tokai-mura, Naka-gun, Ibaraki-ken, 319-11, Japan

Susumu SUGIKAWA Department of Fuel Cycle Safety Research, Japan Atomic Energy Research Institute(JAERI), Tokai-mura, Naka-gun, Ibaraki-ken, 319-11, Japan

Takeshi TSUJINO Department of Fuel Cycle Safety Research, Japan Atomic Energy Research Institute(JAERI), Tokai-mura, Naka-gun, Ibaraki-ken, 319-11, Japan

ABSTRACT

The tri-n-butyl phosphate(TBP) extraction behavior of tritium was studied to support the evaluation of tritium confinement in the Purex process. The tritium distribution ratio in the system of U - 30 % TBP/n-dodecane(nDD) -HNO₃ -H₂O was measured in batch-wise experiments. The tritium decontamination factor in a tritium scrubbing step was measured in chemical flow sheet experiments using a 6 stage mixer-settler having an internal recycle system of aqueous solution in each stage.

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