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    • 71. 发明专利
    • PROCESSING METHOD FOR RADIOACTIVE WASTE LIQUID
    • JPH08271692A
    • 1996-10-18
    • JP6951795
    • 1995-03-28
    • TOSHIBA CORP
    • TOYOHARA NAOMIMIKURA MICHITAKAFUJIHATA KENJIKANEKO MASAAKIWADA MIKIOOKANO TOSHIAKI
    • G21F9/06B01D61/44B01J20/18C02F1/469G21F9/10G21F9/12
    • PURPOSE: To enable reusing neutral salt in a radioactive material treatment facility by decomposing the neutral salt in waste liquid after removing radioactive nuclides into acid and alkali by electric dialysis and recovering them. CONSTITUTION: Waste liquid containing radioactive nuclides is contained in a pH controlling tank 1, acid is supplied from an acid supply tank 2 and pH of the waste liquid is controlled with a pH meter at 5 or less, and the liquid is transported to a coprecipitation reaction tank 4. To this tank, coprecipitation agents, phosphoric acid ion, lanthanum and alkali, 5 to 7, are supplied. At this moment, the supply amount of alkali is monitored with a pH meter 8 to control the waste liquid after adding the coprecipitation agent at pH3 or higher to let the coprecipitation agent precipitate and let the deposition take in TRU nuclides. The waste liquid containing the deposition is filtered with a filter 9 to make the deposition condensed sludge. The waste liquid removed of TRU nuclides together with the deposition is transported to an ion exchanging tower 11 charged with zeolite to remove Cs and tentatively stored in a reservoir tank 12. Then part of the waste liquid is transported to a waste liquid circulation tank 13 and the salt in the waste liquid is decomposed into acid and alkali with an electric dialyzer 14.