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    • 92. 发明专利
    • SOLVENT FOR REPROCESSING
    • JPH05215891A
    • 1993-08-27
    • JP2095392
    • 1992-02-06
    • HITACHI LTD
    • BABA TSUTOMUFUKAZAWA TETSUOKAWAMURA FUMIO
    • G21C19/46G21F9/06
    • PURPOSE:To reduce the elimination frequency of decomposed products and the quantity of a spent-extracted solvent by forming the extracted solvent of a three-component group of TBP/alkane/polar organic solvent. CONSTITUTION:Spent nuclear fuel is led into a feed liquid adjusting process 2 through a dissolving process 1. In the process 2, pH is adjusted to approximately 2.5 in order to obtain the tetravalent form easiest to extract Pu. An extracted solvent adjusted in such a way that the volume ratio of TBP/dodecane/benzene is 3:6:1, for instance, in a solvent adjusting drum 7 is led into a decontamination process 3. In the process 3, 99% or more of a fission product are separated/ removed from U and Pu. An organic polar solvent concentration monitor 8 for monitoring the volume ratio of TBP/dodecan/benzene is installed in a line from the adjusting drum 7 to the process 3. A reducing agent is led into a U-Pu separating process 4. U and Pu are then led into a U and Pu purifying process 6, and the whole spent solvent is led into a solvent cleaning process 5.