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    • 4. 发明专利
    • DEHYDRATING DEVICE
    • JPH04126525A
    • 1992-04-27
    • JP24718390
    • 1990-09-19
    • TOSHIBA CORP
    • SHOJI YUICHIMATSUURA HIROYUKIWADA MIKIO
    • B01D61/56C02F11/12
    • PURPOSE:To dehydrate waste sludge with a static action without any driving part by providing a cation-exchange membrane on the wall of an anode chamber and a cation-exchange membrane and a porous membrane on the wall of a cathode chamber. CONSTITUTION:A cylindrical water collecting pipe 2 is hung at the center in a cylindrical vessel 1, a cathode 11 is provided outside the upper part of the pipe 2, a cathode chamber 13 is formed by a cathode cylinder 12 extending from the cathode 11, and the cation-exchange membrane 14 and a porous membrane 15 adjacent to each other are stuck on the cylinder 12. An anode 16 is provided outside the cathode 11, an anode chamber 18 is formed by the anode and an anode cylinder 17 extending from the anode 16, and a cation- exchange membrane 19 is stuck on the cylinder 17. Sludge is charged into the anode chamber 18 in the vessel 1 which is energized, hence the Na in the sludge entraining water molecule is moved to the cathode and passed through the porous membrane, however the sludge is not passed through the cation- exchange membrane and dehydrated.
    • 5. 发明专利
    • STABILIZING TREATMENT OF RADIOACTIVE WASTE
    • JPH0493798A
    • 1992-03-26
    • JP20917190
    • 1990-08-09
    • TOSHIBA CORP
    • MATSUURA HIROYUKITOYOHARA NAOMIFUJIE MAKOTOSATO TATSUAKI
    • G21F9/08G21F9/10G21F9/16
    • PURPOSE:To enable producing a solidified body which is favorable for safety evaluation thereof by adding a sodium carbonate to a radio-active liquid waste, by applying pretreatment that is to change carbonate ion of a radioactive nuclide, C-14, which exists in a soluble condition in the liquid, to a calcium carbonate, by a slake lime or a quick lime as well as to refractory carbonate, at the same time, and also by applying drying-up treatment and solidification. CONSTITUTION:Concentrated readioactive liquid waste is pre-treated by a sodium carbonate. Soluble cabonate ion existing in a form of a sodium cabonate in the liquid waste, is changed to a calcium carbonate and to a refractory condition into water. However, since an amount of the carbonate ion containing a radioactive nuclide, C-14, is extremely small, the cabonate reaches its solubility and therefore there is some possibility to be dissolved into water, even if such a pre-treatment is applied. Accordingl, a sodium carbonate is previously added to the extent that the solubility of the calcium carbonate is well exceeded, and there with the carbonate ion containing the nuclide, C-14, co-precipitates with the added carbon ion ad then can be changed to almost insoluble one into water. Finally, the ion is treated by a plastic solidification process or a pelletizing treatment.