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    • 31. 发明专利
    • METHOD FOR TREATING RADIOACTIVE LIQUID WASTE
    • JPH11118990A
    • 1999-04-30
    • JP28005897
    • 1997-10-14
    • HITACHI LTD
    • NOSHITA KENJINISHI TAKASHIYUKITA ATSUSHIMATSUDA MASAMI
    • G21F9/16
    • PROBLEM TO BE SOLVED: To dissolve a large amount of boron by an evaporation condensation process, suppress the deposition of boric acid salt, and at the same time achieve a high- magnification condensation by increasing the pH of liquid waste in an alkali addition process larger than 12. SOLUTION: After a boric acid liquid waste is supplied to a pH adjustment tank 4, a valve 6 is opened and sodium hydroxide in an alkali storage tank 5 is supplied to the tank 4. In the meantime, an agitator 7 is driven, thus agitating the boric acid liquid waste and NaOH and making uniform the composition. Then, a solution where pH is adjusted to at least 13 is supplied into a total amount condenser 10 by opening a valve 9. After that, the solution is heated at 100 deg.C under the atmosphere by a heater 10a and is subjected to evaporation condensation treatment, thus setting a boron concentration to approximately 150 g/L. More specifically, the amount of the solution is condensed from 3,000 L to approximately 100 L, which is approximately 30 times larger. After the condensed liquid is supplied to a kneading machine 12, a specific amount of ordinary portland cement in a curing material tank 13 is supplied to the kneading machine 12. By setting pH to 13 or more before curing, the curing reaction of cement can be promoted preferentially due to the precipitation reaction caused by boric acid ion.
    • 32. 发明专利
    • SOLIDIFICATION PROCESSING METHOD OF RADIOACTIVE WASTE
    • JPH10227895A
    • 1998-08-25
    • JP3004197
    • 1997-02-14
    • HITACHI LTD
    • NOSHITA KENJINISHI TAKASHI
    • G21F9/16
    • PROBLEM TO BE SOLVED: To improve holding performance for radioactive iodine of radioactive waste solid body by adding an oxidizing agent of a specific concentration in the case of solidifying processing radioactive waste with a cement group solidifier agent. SOLUTION: In solidifying processing, condensed waste liquid is supplied form a waste liquid tank 1 through a constant amount supply device 4 to a kneader 5 and a cement group solidifying agent is supplied from a solidifying agent tank 2 through a quantifying supply device 6 to the kneader 5. The oxidizing agent is supplied so as to be 0.01mol for 100g of waste solid weight from a oxidizing agent tank 3 through a constant amount supply device 7 to the kneader 5. For oxidizing agent, peroxodisulfate, silver oxide, permanganate or dichromate are used. After sufficiently mixing with the kneader 5, the cement paste of the condensed waste liquid is injected in a solidifying vessel 9 with an electromagnetic valve 8 and is statically cured for ca. a month. By this, holding capability of radioactive iodine of solid by cement group solidifying agent can be improved.
    • 35. 发明专利
    • DISPOSAL METHOD OF RADIOACTIVE WASTE
    • JPH08129100A
    • 1996-05-21
    • JP26653294
    • 1994-10-31
    • HITACHI LTD
    • NOSHITA KENJIMATSUDA MASAMINISHI TAKASHIKOMORI ITARUMATSUO TOSHIAKIIZUMIDA TATSUO
    • G21F9/30
    • PURPOSE: To reduce residual coverage onto a disposal equipment by crushing massive radioactive waste, mixing the crushed waste with a solidifying material and infecting the mixture into a solidifying container. CONSTITUTION: When incinerated ash in a storage container 1 is charged into an incinerated-ash hopper 4 and a valve 5 is opened, the inside of a cage type rotor for a crusher 6 is supplied with incinerated ash. Moistened massive incinerated ash is shocked by pin shields, in which adjacent rows in the rotor are rotated in the opposite directions mutually, and crushed. Incinerated ash, in which massive ash is crushed completely, is introduced into a screw feeder 7, and the inside of a kneading machine 8 is supplied with incinerated ash by driving the feeder 7. Incinerated ash fed into the kneading machine 8 is kneaded with previously charged cement paste by an agitator 13, the inside of a solidifying container 15 is fed with these mixtures through an outlet piping by opening a solenoid valve 14, an upper end is sealed with a cover, and the solidifying container 15 is carried into a solidifying-container storage region.
    • 38. 发明专利
    • SOLIDIFYING METHOD OF RADIOACTIVE WASTE
    • JPH06180393A
    • 1994-06-28
    • JP33409392
    • 1992-12-15
    • HITACHI LTD
    • NOSHITA KENJIMATSUDA MASAMINISHI TAKASHIKOMORI ITARU
    • G21F9/30
    • PURPOSE:To increase the elution rate of cation while reducing treatment cost using normal cement by performing solidification on condition that bivalent cations of Ca are increased for the cement at the time of hardening reaction. CONSTITUTION:A water hardening inorganic solidification material is subjected to main hardening process where water reacts on the surface of the hardening material to produce a hydrate from which bivalent cations of Ca are then eluted. The reaction progresses gradually into the solidifying material and sustains until the bivalent cation of Ca exceeds a saturable solubility. When the saturable solubility is exceeded, Ca(OH)2 is deposited on the surface of the solidifying material. At that time, concentration of bivalent cation of Ca in the liquid increases and a part of cations of Ca stays in the solidifying material thus creating a gel phase of CaO-SiO2-H2O. Consequently, hardening is ended within a normal interval by adding a Ca compound having high solubility or increasing elution rate of bivalent cation of Ca from the solidifying material through high temperature curing.
    • 39. 发明专利
    • METHOD FOR SOLIDIFYING RADIOACTIVE WASTE
    • JPH05312996A
    • 1993-11-26
    • JP12322392
    • 1992-05-15
    • HITACHI LTD
    • NOSHITA KENJIMATSUDA MASAMINISHI TAKASHIKOMORI ITARU
    • B09B3/00G21F9/16
    • PURPOSE:To reduce hydrogen generation due to radiation decomposition and improve the long term soundness of a solid by controlling the organic substance concentration in the solid. CONSTITUTION:Due to radiation decomposition of water contained in a solid body, hydrogen is generated. The hydrogen generation rate per unit of radiation is affected by organic substances contained as impurity in hydraulic-setting inorganic hardening agent. Thus, in a solidifying agent tank 1, the hydraulic- setting inorganic solidifying agent as a solidifying agent and various additives are sufficiently mixed at proper mixing ratio and stored. After eliminating organic substances from this solidifying agent powder with an organic substance elimination device, a constant amount of powder is supplied to a mixer 6 with a constant amount conveyer 3 and sufficiently mixed with mixing water from a mixing water tank 4 to form a paste. After injecting this paste in a solidifying vessel 8 containing miscellaneous solids 9, a vessel lid is put on to leave it for a month until a solid is made. In this process in the device 2, organic matter is eliminated to lower than ca. 500ppm concentration by using a filter, aborption agent, burner and chemical reactions, etc., to improve the long term soundness of the solid.