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    • 31. 发明专利
    • Radioactive waste liquid treatment apparatus and method
    • 放射性废液处理装置及方法
    • JP2007003270A
    • 2007-01-11
    • JP2005181792
    • 2005-06-22
    • Toshiba Corp株式会社東芝
    • HARUGUCHI YOSHIKOMIKURA MICHITAKAMURATA EIICHISATO TATSUAKISAKURAI JIROTAKADA TAKAO
    • G21F9/10G21F9/06G21F9/16
    • PROBLEM TO BE SOLVED: To enhance a separation efficiency in operation of separating a radionuclide by controlling the valency of iron in a radioactive waste liquid and then changing iron into iron oxide. SOLUTION: A radioactive waste liquid treatment apparatus comprises a waste liquid tank 1 wherein the pH of the waste liquid is controlled by using a pH conditioner fed from a pH conditioner tank 3 and iron ions contained in the waste liquid are reduced by a reducing agent fed from a reducing agent tank 2 while the liquid is being heated, a conversion tank 5 provided with a temperature control facility 4 wherein the pH of the waste liquid is controlled by using the pH conditioner fed from the pH conditioner tank 3 and iron hydroxide in the reduced radioactive waste liquid fed from the waste liquid tank 1 is converted into iron oxide, a solid-liquid separator 6 for executing the solid-liquid separation of the radioactive waste liquid fed from the conversion tank 5 into a supernatant liquid and residue, a supernatant liquid accepting tank 7 for storing the supernatant liquid fed from the solid-liquid separator 6 and a sludge tank 8 for storing the residue fed from the solid-liquid separator 6. COPYRIGHT: (C)2007,JPO&INPIT
    • 要解决的问题:通过控制放射性废液中的铁的价态,然后将铁变成氧化铁来提高分离放射性核素的分离效率。 解决方案:放射性废液处理装置包括:废液罐1,其中通过使用从pH调节剂罐3供给的pH调节剂和废液中含有的铁离子来控制废液的pH, 设置有温度控制装置4的转换槽5,其中通过使用从pH调节剂罐3供给的pH调节剂和铁调节剂来控制废液的pH, 将从废液罐1供给的放射性废弃废液中的氢氧化物转化成氧化铁,将从转化罐5供给的放射性废液的固液分离成上清液和残渣的固液分离器6 ,用于储存从固液分离器6供给的上清液的上清液接收槽7和用于储存从固液分离器6供给的残留物的污泥槽8 作者6.版权所有(C)2007,JPO&INPIT
    • 35. 发明专利
    • Method for treating used ion-exchange resin
    • 处理使用离子交换树脂的方法
    • JP2012088330A
    • 2012-05-10
    • JP2011282813
    • 2011-12-26
    • Toshiba Corp株式会社東芝
    • HARUGUCHI YOSHIKOTAKAHASHI RYOTAKANEKO MASAAKIYAMASHITA TAKEOSATO TATSUAKIMIKURA MICHITAKAARIMA YUKI
    • G21F9/30
    • PROBLEM TO BE SOLVED: To provide a method for treating an used ion-exchange resin which can dispose of the used ion-exchange resin more efficiently at a lower cost than that of the prior art.SOLUTION: In a method for treating an used ion-exchange resin, an ion-exchange group disabling process for disabling ion-exchange groups is performed on an used (sulfonic acid-based) ion-exchange resin 1 on which radionuclides 2 are adsorbed. Either alkali fusion by a strongly basic salt or reduction treatment is used as the ion-exchange group disabling process. The radionuclides 2 are desorbed from the used ion-exchange resin 1 by the ion-exchange group disabling process. Subsequently, the used ion-exchange resin 1a from which the radionuclides 2 have been desorbed and a liquid for reaction containing the desorbed radionuclides 2 are separated.
    • 要解决的问题:提供一种处理使用的离子交换树脂的方法,其可以以比现有技术更低的成本更有效地处理使用的离子交换树脂。 解决方案:在用于处理使用的离子交换树脂的方法中,对使用的(磺酸系)离子交换树脂1进行离子交换基团的禁用离子交换基团残留处理,其中放射性核素2 被吸附。 使用通过强碱性盐或还原处理的碱熔融作为离子交换组禁用方法。 放射性核素2通过离子交换组禁用处理从使用的离子交换树脂1解吸。 随后,将已经脱离了放射性核素2的已使用的离子交换树脂1a和含有解吸附的放射性核素2的反应液分离。 版权所有(C)2012,JPO&INPIT
    • 36. 发明专利
    • Method and device for treating waste water containing boric acid
    • 用于处理含有挥发性酸的废水的方法和装置
    • JP2012058034A
    • 2012-03-22
    • JP2010200269
    • 2010-09-07
    • Toshiba Corp株式会社東芝
    • SATO TATSUAKISHOJI YUICHIYAGI MAIKOMIKURA MICHITAKAAISAKA TAKASHISAKURAI MANABUSEKI HIDEJI
    • G21F9/16G21F9/06G21F9/08G21F9/10
    • PROBLEM TO BE SOLVED: To provide a new method and a device for treating waste water containing boric acid capable of preventing piping from being blocked in a drying process of borate generated by insolubilization of boric acid in waste water.SOLUTION: The present invention comprises: a first step to insolubilize boric acid in a manner that precipitates the same contained in waste water as insoluble borate in a first tank; a second step to store the waste water with the insolubilized borate in a second tank having an agitation mixer; a third step to transfer the waste water with the insolubilized borate from the second tank to a dryer to separate the borate from the waste water by drying; a fourth step to produce condensed water containing a portion of the borate by condensing steam which is generated in the dryer and contains the portion of the borate with a cooling device; and a fifth step to remove the portion of the borate in the condensed water by a purifier.
    • 要解决的问题:提供一种用于处理含硼酸的新方法和装置,其能够防止管道在通过废水中硼酸不溶化而产生的硼酸盐的干燥过程中被堵塞。 解决方案:本发明包括:使硼酸不溶解的方法,该方法是使第一罐中的不溶性硼酸盐沉淀在废水中; 在具有搅拌混合器的第二罐中将废水与不溶硼酸盐一起存储的第二步骤; 将不溶硼酸盐的废水从第二罐转移到干燥器的第三步骤,通过干燥将硼酸盐与废水分离; 第四步骤,通过冷凝干燥器中产生的含有一部分硼酸盐的冷却装置来产生含有一部分硼酸盐的冷凝水; 以及通过净化器除去冷凝水中的部分硼酸盐的第五步骤。 版权所有(C)2012,JPO&INPIT
    • 39. 发明专利
    • Method and device for treating radioactive liquid waste
    • 用于处理放射性液体废物的方法和装置
    • JP2004085249A
    • 2004-03-18
    • JP2002243697
    • 2002-08-23
    • Toshiba Corp株式会社東芝
    • MIYAMOTO MASAYAYAITA YUMISATO TATSUAKIKANEKO MASAAKITODA MASAMIMIKURA MICHITAKATAKADA TAKAO
    • G21F9/06G21F9/16
    • PROBLEM TO BE SOLVED: To turn organic substances into inorganic substances, containing a concentrated liquid waste of a waste resin in a reactor water purification system generated in nuclear power generating facilities and the like, and to treat them to yield stable cement solidified body.
      SOLUTION: In a method for treating a concentrated liquid waste of a radioactive waste resin containing sodium sulfate solution, the organic substances contained in the concentrated liquid waste are turned into inorganic substance through ozone oxidation, and then cement is added to solidify them. Moreover, a treatment device for treating the liquid waste prior to the concentrated liquid waste of the radioactive waste resin containing the sodium sulfate solution is cemented, has a reaction vessel 10 accommodating the concentrated liquid waste, an ozone gas blowout pipe 9 submerged in the concentrated liquid waste in the reaction vessel 10, and an ozone generator 8 supplying ozone to the ozone gas blowout pipe 9.
      COPYRIGHT: (C)2004,JPO
    • 要解决的问题:将有机物质转化为在核发电设备等中产生的反应堆水净化系统中含有废树脂的浓缩废液的无机物质,并且对它们进行处理以产生稳定的水泥固化 身体。 解决方案:在用于处理含硫酸钠溶液的放射性废物树脂的浓缩废液的方法中,通过臭氧氧化将浓缩废液中含有的有机物质变成无机物质,然后加入水泥固化 。 此外,在含有硫酸钠溶液的放射性废物树脂的浓缩废液之前处理液体废物的处理装置被胶合,具有容纳浓缩废液的反应容器10,浸没在浓缩的废水中的臭氧气体吹出管9 反应容器10中的废液以及向臭氧气体吹出管9供给臭氧的臭氧发生器8。(C)2004,JPO
    • 40. 发明专利
    • Method and apparatus for processing radioactive waste, and its solidifying method
    • 用于处理放射性废物的方法和装置及其固化方法
    • JP2003294888A
    • 2003-10-15
    • JP2002094111
    • 2002-03-29
    • Toshiba Corp株式会社東芝
    • HODOZUKA MASATOSHITOYOHARA NAOMIMIKURA MICHITAKAMURATA EIICHIKANEKO MASAAKITAKAHASHI RIYOUTASAKAI HIROHIKO
    • G21F9/06G21F9/02G21F9/10G21F9/16
    • PROBLEM TO BE SOLVED: To reuse salt waste produced by a dry-type reprocessing method, or to solidify it. SOLUTION: When spent fuel is reprocessed by the dry method, waste of fused salt being an chloride of alkaline metal is produced. After this waste 1 of spent fused salt is dissolved 2 in water, this aqueous solution is electrolytically dialyzed 3. Consequently, impurities are removed, and fused salt being a chloride of alkaline metal is recovered as an aqueous solution of a hydroxide of the alkaline metal. The recovered aqueous solution is caused to react with hydrochloric acid, and is reused again as fused salt. The recovered processed solution 4 is solidified and reused 5. Namely, it is solidified into waste, or it is reacted with phosphoric acid to produce phosphate, and the phosphate is vitrified. COPYRIGHT: (C)2004,JPO
    • 要解决的问题:重新使用由干式再加工方法生产的盐类废物或使其固化。

      解决方案:当废燃料通过干法再处理时,产生作为碱金属氯化物的熔融盐的浪费。 废弃的1熔融盐溶解后,将该水溶液2溶解在水中,将该水溶液进行电解透析3.因此,除去杂质,作为碱金属的氢氧化物的水溶液回收作为碱金属的氯化物的熔融盐 。 使回收的水溶液与盐酸反应,并再次作为熔融盐再次使用。 回收的处理溶液4固化并重新使用5.即,其被固化成废物,或者与磷酸反应以产生磷酸盐,并且磷酸盐被玻璃化。 版权所有(C)2004,JPO