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2000•Doryoku, Enerugi Gijutsu Shinpojiumu koen ronbunshu/Doryoku, enerugi gijutsu no saizensen koen ronbunshuOpen access

Development of Spent Fuel Reprocessing by Super-critical Fluid : Development of Super DIREX Method

Takashi Shimada, Shinya Ogumo, Yukihide Mori, Nobuo Ishihara, Yuji Kosaka, Kunihiro Ito

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Abstract

Supercritical fluid DIRect Extraction (Super-DIREX) Method has been developed, and it is the technique of extracting Uranium and Plutonium elements directly from spent fuel oxides by supercritical CO_2 containing HNO_3-tributylphosphate (TBP) complex (at 313K-333K and 10-20MPa). From this study, it is concluded that the reprosessing system adopting Super-DIREX Method is more simple and unexpensive than PUREX system. The experiment was carried out by using test piece including irradiation Uranium oxide and imitative fission product (FP) elements oxide, and the results showed that Uranium could be extracted in separating from FP elements at 313K and 12MPa and that one step extraction by Super DIREX Method could get more than 100 of decommission factor (DF) of the FP elements.

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Supercritical fluid DIRect Extraction (Super-DIREX) Method has been developed, and it is the technique of extracting Uranium and Plutonium elements directly from spent fuel oxides by supercritical CO_2 containing HNO_3-tributylphosphate (TBP) complex (at 313K-333K and 10-20MPa). From this study, it is concluded that the reprosessing system adopting Super-DIREX Method is more simple and unexpensive than PUREX system. The experiment was carried out by using test piece including irradiation Uranium oxide and imitative fission product (FP) elements oxide, and the results showed that Uranium could be extracted in separating from FP elements at 313K and 12MPa and that one step extraction by Super DIREX Method could get more than 100 of decommission factor (DF) of the FP elements.

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Available abstract

Supercritical fluid DIRect Extraction (Super-DIREX) Method has been developed, and it is the technique of extracting Uranium and Plutonium elements directly from spent fuel oxides by supercritical CO_2 containing HNO_3-tributylphosphate (TBP) complex (at 313K-333K and 10-20MPa). From this study, it is concluded that the reprosessing system adopting Super-DIREX Method is more simple and unexpensive than PUREX system. The experiment was carried out by using test piece including irradiation Uranium oxide and imitative fission product (FP) elements oxide, and the results showed that Uranium could be extracted in separating from FP elements at 313K and 12MPa and that one step extraction by Super DIREX Method could get more than 100 of decommission factor (DF) of the FP elements.

Key concepts: PUREX, Plutonium, Supercritical fluid, Uranium, Fission products, Extraction (chemistry), Spent nuclear fuel, Nuclear fuel

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