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    • 2. 发明专利
    • METHOD AND DEVICE FOR DISPOSING OF RADIOACTIVE WASTE
    • JPH10206594A
    • 1998-08-07
    • JP837697
    • 1997-01-21
    • HITACHI LTD
    • NISHI TAKASHINOSHITA KENJISASAHIRA AKIRAIZUMIDA TATSUO
    • G21F9/00G21F9/02
    • PROBLEM TO BE SOLVED: To reduce the corrosion of a heating furnace and improve the recovery of radioactive substances by heating a radioactive waste containing volatile radioactive substances under a reduced pressure, condensing the radioactive substances after vaporizing and separating them and then recovering them in a liquid or solid state. SOLUTION: A waste 2 is loaded into a heating container 1, which is sealed up, a valve 8 is opened, a vacuum pump 10 is actuated and the pressure inside the heating container 1, a condensation pipe 4 and a recovery container 7 is reduced to a set degree of a vacuum with attention paid to a vacuum pressure gauge 9. Then, heaters 3 and 5 are heated up to prescribed temperatures respectively. In case of the recovery of only cesium from the waste 2 contaminated by radioactive cesium, for example, the temperature of the heaters 3 and 5 are set at about 900 deg.C and about 700 deg.C respectively of the set degree of a vacuum is about 10 Torr. Such decompression can reduce the vaporizing temperature of radioactive substances from the waste 2 and can also accelerate the vaporization of the radioactive substances which have permeated inside microprobes of the waste 2. Therefore, it is possible to reduce the corrosion of a heating furnace and improve a decontamination factor.
    • 6. 发明专利
    • SOLIDIFICATION OF WASTE
    • JPH02162298A
    • 1990-06-21
    • JP31641388
    • 1988-12-16
    • HITACHI LTDHESCO
    • IZUMIDA TATSUONISHI TAKASHIBABA TSUTOMUCHINO KOICHIKIUCHI YOSHIMASATSUCHIYA HIROYUKI
    • G21F9/16G21F9/00
    • PURPOSE:To make it unnecessary to accelerate a hardening speed by adding a cement typed hardening agent and to obtain a low cost and high safety solidified body, by using an inorganic water absorbent of which absorption speed is greater than a dissolving speed, in a paste, of a water soluble organic substances. CONSTITUTION:A condensed waste liquid 1 is fed to a dryer mill 2, where inorganic substances such as a sodium nitrate are dried and milled, and an pelletized by a pelletizer 3 as a next processing stage. A constant amount of pellets 4 is fed to a solidifying bin 7 by a measuring feeder 6 of pellets after a temporary storage in a pellet receiver 5. Constant amounts of a water setting hardener 8, an inorganic water absorbent 9 and water 10 are fed to a kneader 15 through tanks 11 to 13 and measuring feeders 14, respectively, and a paste 16 to be solidified, is produced by a mixing vane 17. The paste 16 is injected into the bin 7 which is filled with the pellets, through a valve 13, to fill out spaces among the pellets. A solidified body 18 is produced by statically placing and curing the bin 7. When the controlling of the paste 16 temperature is required, a heat exchanger 12 placed at the kneader 15, is operated.
    • 7. 发明专利
    • SOLIDIFICATION OF RADIOACTIVE WASTE AND ITS DEVICE
    • JPH02141698A
    • 1990-05-31
    • JP29689688
    • 1988-11-24
    • HITACHI LTD
    • NISHI TAKASHIIZUMIDA TATSUOFUNABASHI KIYOMIBABA TSUTOMUCHINO KOICHI
    • G21F9/16G21F9/00G21F9/30G21F9/36
    • PURPOSE:To lower the leaching rate of radioactivity and shorten the time required for a radioactive contamination to reach the surface of a solidified body by adapting a wetting treatment to a concrete surface of a container prior to injecting a water setting solidifying agent into the container of which inner surface is lined with a concrete layer and the like. CONSTITUTION:First of all, water is filled in a dry concrete container for a predetermined period and then the water is drained by tilting the container to make the dry container be a wet concrete one. After that, an appropriate amount of radioactive solid wastes are filled into the wet concrete container. Then, a water setting solidifying agent in a form of a paste mixed fully with water is injected. The agent is injected to a level several centimeters above an uppermost level of the waste in the container and then a concrete-made floating lid is placed on it and finally the agent is poured on the lid and is left for about one month at a condition of a wet curing. With this procedure, moving-around of radioactive nuclides caused by a capillarity permeation of mixing water can be prevented, and a lowering of a leaching rate of a radioactivity and the like can be attained.
    • 8. 发明专利
    • METHOD FOR CONCENTRATING WASTE NITRIC ACID SOLUTION
    • JPH01114799A
    • 1989-05-08
    • JP27377887
    • 1987-10-29
    • HITACHI LTD
    • IZUMIDA TATSUOSASAHIRA AKIRATAKAHASHI MASANORIKAWAMURA FUMIO
    • G21F9/08G21F9/00
    • PURPOSE:To decrease the concn. of the nitric acid in a waste nitric acid liquid contg. radioactive nuclides in large quantity by a simple technique in a short period of time by subjecting the high-concn. nitric acid after vacuum concentration further to vacuum evaporation while supplying heat-decomposable aq. alkaline soln. CONSTITUTION:The waste nitric acid liquid contg. the radioactive nuclides is supplied from a raw material nitric acid tank 6 into a nitric acid concentrating vessel 1 and is heated by a heater 4. The concentration system supplies the waste liquid from the tank 6 continuously into the vessel 1 evacuated to a reduced pressure by a vacuum evacuation device 10 at the point of the time when the vapor begins to condense in a condenser 8 by passing a mist separator 3 on progressing of the evaporation in said vessel. The system continues the vacuum evaporation while maintaining the specified evaporation rate from the vessel 1 by controlling a power supply 5 for heating the heater. The water and nitric acid evaporating from the vessel 1 are condensed in the condenser 8, are further refined in a nitric acid refining device 11 and are separated to the recovered water and the recovered nitric acid. The concentrated vessel liquid 2 is thereby linearly increased in the concn. of the metal ions of the radioactive nuclides. The concn. of the nitric acid is sharply decreased if the vacuum evaporation is further continued while an aq. soln. of strongly alkaline aliphat. amine is supplied to the vessel from an aq. alkaline soln. tank 15.