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    • 1. 发明专利
    • METHOD AND DEVICE FOR TREATING WASTE CONTAINING BORON
    • JP2000284092A
    • 2000-10-13
    • JP2000016776
    • 2000-01-26
    • TOSHIBA CORPTOSHIBA ENGINEERING CO
    • TOYOHARA NAOMISATO TATSUAKINODA TETSUYASUZUKI NORIKOTAKAMATSU YOSHINARI
    • G21F9/16G21F9/08
    • PROBLEM TO BE SOLVED: To make it possible to prevent a liquid waste line from clogging by keeping the temperature to the point of adding a compound of alkali metal elements and that of an alkaline earth metal element to a liquid waste containing boron, and drying and powdering a mixture of them at the deposition temperatures of boron and both compounds or higher. SOLUTION: After a radioactive liquid waste 1 containing boric acid as a main constituent that is generated in a nuclear power plant is heated 2 at the temperature of 80 deg.C or higher, the liquid waste 1 is neutralized by adding a compound 3 of alkali metal elements such as Na and K to the liquid waste. Moreover, the boric acid as the main constituent is insolubilized by adding a compound 4 of alkaline earth metal elements such as Ca and Mg to the liquid waste 1. Then, a liquid waste containing an insoluble compound of a boric acid (a liquid waste containing an insoluble boric acid) obtained in the previous process is supplied to a dryer while keeping the temperature of the liquid waste at 80 deg. C or higher, a drying treatment 5 is carried out for the liquid waste to convert it to dried powder 6 and the volume of it is reduced. In this process, the sedimentation velocity of insoluble borate in the liquid waste can be reduced by keeping the temperature of the liquid waste at 80 deg.C or higher, which makes it possible to prevent a liquid waste line from clogging. The dried powder 6 is solidified in concurrence with a cementitions material.
    • 2. 发明专利
    • RADIOACTIVE WASTE LIQUID DISPOSAL SYSTEM
    • JP2002139595A
    • 2002-05-17
    • JP2000330348
    • 2000-10-30
    • TOSHIBA ENGINEERING COTOSHIBA CORP
    • ISHII TOMOHARUNODA TETSUYA
    • G21F9/06G21F9/04G21F9/28
    • PROBLEM TO BE SOLVED: To shorten the disposal time and improve the reliability of filtrate quality by monitoring the state of a cake layer formed within a filter. SOLUTION: A pump 2 and the filter 3 are connected to a radioactive waste liquid collecting tank 1 through piping. A turbidmeter 8 is set in the filtrate discharging pipe 18 of the filter 3. The outlet side of the turbidmeter 8 is connected to a sump tank 4 through a sump tank inlet valve 21. The sump tank inlet valve 21 is remotely opened and closed by a measurement control device 11. One side of a return pipe 5 branched from the sump tank inlet valve 21 is connected to the outlet side of the turbidmeter 8, and the other is connected to the collecting tank 1. A collecting tank return valve 20 remotely opened and closed by the measurement control device 11 is set in the return pipe 5. A cake discharge valve 19 is connected to the cake discharge side of the filter 3, and a metal drum 6 is connected to the downstream side from the cake discharge valve 19. A powdery activated charcoal feeder 7 is connected to the collecting tank 1.
    • 4. 发明专利
    • RADIOACTIVE WASTE LIQUID PROCESSING DEVICE
    • JPH1062595A
    • 1998-03-06
    • JP21819796
    • 1996-08-20
    • TOSHIBA ENGINEERING COTOSHIBA CORP
    • HARA SATOMINODA TETSUYA
    • G21F9/10
    • PROBLEM TO BE SOLVED: To make a backwash operation of filter, simplify operation action by avoiding a backwash water transport pipe and reduce the equipment size reducing the capacity of sludge storage. SOLUTION: Downstream of an LCW collection tank 5 accepting radioactive waste liquid containing sludge 4 in a sedimentation tank 2, a rotary filter 24 is arranged instead of conventional LCW filter device assembled with hollow fiber membrane filter. With this rotary filter 24, the sludge 4 in radioactive waste liquid from the LCW collection tank 5 is filtered. By this, backwash operation conducted with hollow fiber member filter becomes unnecessary and providing a backwash water line returning the backwash water to the sedimentation tank 2 is not required. Thus, operation action for this is simplified and the equipment can be reduced in size. Besides, as the sludge filtered in the rotary filter 24 can be stored directly in a drum 25, the extraction process of sludge 4 from the sedimentation tank 2 becomes unnecessary.
    • 5. 发明专利
    • RADIOACTIVE WASTE LIQUID TREATMENT SYSTEM
    • JPH09133793A
    • 1997-05-20
    • JP29391695
    • 1995-11-13
    • TOSHIBA CORPTOSHIBA ENGINEERING CO
    • NODA TETSUYAKURAMITSU KIMINORIISHII TOMOHARU
    • G21F9/06
    • PROBLEM TO BE SOLVED: To make a facility compact, reduce a maintenance work for equipment, lower the extent of exposure to a radiation and reduce the generation of a waste material by improving and recovering a treatment flowrate. SOLUTION: A filter 3 is connected to a collection tank 1 via a pump 2, and a sump tank 4 is connected to the outlet of the filter 3. The outlet of the filter 3 is connected to the collection tank 1 via a return pipe 5, and the cake delivery side of the filter 3 is connected to a drum 6. Also, an activated powder carbon feeder 7 is connected to the collection tank 1, and a chemical tank 8 is connected to the collection tank 7 and the filter 3 via chemical feed lines 12 and 9. Furthermore, the filter 3 has agitation vanes (b) and agitation liquids (c) alternately arranged in a filtration chamber (a) at a small gap, and the agitation vanes (b) rotate at a constant speed on the rotation of a motor (d). Also, a filter board (c) has a filtrated liquid discharge mechanism (e) and filter cloth is attached to both side of the filter board (c). In addition, a filter vent 10 and a filter drain 11 are connected to the outlet of the filter 3.
    • 10. 发明专利
    • TREATING METHOD FOR RADIOACTIVE WASTE LIQUID
    • JPH0387700A
    • 1991-04-12
    • JP22328689
    • 1989-08-31
    • TOSHIBA CORP
    • YASUMURA KEIJIRONISHIKI YOSHIENODA TETSUYA
    • G21F9/12B01J20/34C01B31/08
    • PURPOSE:To efficiently eliminate a soluble substance and an insoluble substance from a radioactive waste liquid of low radioactive concentration by treating the radioactive waste liquid by activated carbon, and reproducing the activated carbon by hydrogen peroxide and reusing it, when the suction capacity of the activated carbon is deteriorated. CONSTITUTION:First of all, a dummy waste liquid is supplied to a feed liquid tank 1, and by operating a pump 2, a valve V1 is opened, and the dummy waste liquid is supplied to an activated carbon filling vessel 3. Subsequently, COD of treating water is measured by a chemical oxygen demand meter (COD meter) installed in an outlet of the vessel 3, and at the time point when the COD reaches a prescribed value or above, the pump 2 is stopped. Next, the valve V1 is closed, a pump 7 is driven, a valve V3 is opened, and hydrogen peroxide is supplied by a prescribed quantity to the vessel 3. After this state is left as it is about 10 - 30 hours, the valve V3 is closed, a valve V2 is opened and hydrogen peroxide is exhausted to a used hydrogen peroxide receiving tank 8. After closing the valve V2 and V3, the valve V1 is opened, and by operating the pump 2, a waste liquid is supplied to the vessel 3 again, and the same operation is repeated.