会员体验
专利管家(专利管理)
工作空间(专利管理)
风险监控(情报监控)
数据分析(专利分析)
侵权分析(诉讼无效)
联系我们
交流群
官方交流:
QQ群: 891211   
微信请扫码    >>>
现在联系顾问~
热词
    • 31. 发明专利
    • Treatment method and treatment apparatus of radioactive waste
    • 放射性废物处理方法及处理装置
    • JP2012225682A
    • 2012-11-15
    • JP2011091303
    • 2011-04-15
    • Toshiba Corp株式会社東芝
    • SATO TATSUAKISHOJI YUICHIHARUGUCHI YOSHIKOMIKURA MICHITAKAYASUMURA KEIJIRO
    • G21F9/16G21F9/28G21F9/30
    • PROBLEM TO BE SOLVED: To remove and wash attached substances derived from cement kneaded mixture attached to an agitation blade without generating new radioactive waste when treating radioactive waste by kneading and mixing the radioactive waste and cement by the agitation blade in a predetermined container to obtain cement kneaded mixture and solidifying the cement kneaded mixture.SOLUTION: Radioactive waste and cement are kneaded and mixed by an agitation blade 12 in a container 11 including the agitation blade 12 to obtain cement kneaded mixture including the radioactive waste and the cement. Then attached substances derived from the cement kneaded mixture attached to the agitation blade 12 are removed and washed by spraying gas from a predetermined ejector 15 to the attached substances. Then the cement kneaded mixture is solidified to obtain a cement solid.
    • 待解决的问题:通过在预定的容器中搅拌和混合放射性废物和水泥,通过搅拌叶片处理放射性废物,除去和洗涤附着在搅拌叶片上的水泥捏和混合物的附着物质,而不会产生新的放射性废物 获得水泥捏合混合物并固化水泥捏合混合物。 解决方案:放射性废物和水泥通过搅拌叶片12在包括搅拌叶片12的容器11中捏合和混合,以获得包括放射性废物和水泥的水泥捏和混合物。 然后除去附着在搅拌叶片12上的来自水泥混炼混合物的附着物质,将预定的喷射器15的气体喷雾到附着物上。 然后将水泥捏合混合物固化,得到水泥固体。 版权所有(C)2013,JPO&INPIT
    • 32. 发明专利
    • Method and device for processing waste ion exchange resin
    • 用于处理废物离子交换树脂的方法和装置
    • JP2012103145A
    • 2012-05-31
    • JP2010252509
    • 2010-11-11
    • Toshiba Corp株式会社東芝
    • YASUMURA KEIJIROSATO TATSUAKIMIKURA MICHITAKAHARUGUCHI YOSHIKOMIYAMOTO MASAYASUZUKI SHOTAHARA TOSHIO
    • G21F9/30B09B3/00C08J11/16
    • Y02W30/705
    • PROBLEM TO BE SOLVED: To stably perform disposal of waste ion exchange resin without damaging a cement-solidified object by preventing swelling of the waste ion exchange resin when processing the waste ion exchange resin containing weakly basic ion exchange resin used in a nuclear facility by cement-solidifying the waste ion exchange resin.SOLUTION: A method for processing the waste ion exchange resin containing the weakly basic ion exchange resin includes a step of heating the waste ion exchange resin while immersing the waste ion exchange resin in alkali aqueous solution, and degrading amino bases of the weakly basic ion exchange resin in the waste ion exchange resin; and a step of cement-solidifying the waste ion exchange resin.
    • 要解决的问题:为了稳定地进行废弃离子交换树脂的处理,而不损害水泥固化物体,通过防止废物离子交换树脂在处理含有用于核中的弱碱性离子交换树脂的废离子交换树脂时的溶胀 通过水泥固化废物离子交换树脂的设备。 解决方案:用于处理含有弱碱性离子交换树脂的废离子交换树脂的方法包括在将废离子交换树脂浸入碱水溶液中的同时加热废离子交换树脂并降解弱碱性氨基的步骤 废离子交换树脂中的碱性离子交换树脂; 以及将废弃离子交换树脂水泥固化的步骤。 版权所有(C)2012,JPO&INPIT
    • 33. 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
    • JP2012058033A
    • 2012-03-22
    • JP2010200268
    • 2010-09-07
    • Toshiba Corp株式会社東芝
    • SATO TATSUAKISHOJI YUICHIYAGI MAIKOMIKURA MICHITAKAAISAKA TAKASHISAKURAI MANABU
    • G21F9/16G21F9/06G21F9/08G21F9/10
    • PROBLEM TO BE SOLVED: To provide a method and a device for treating waste water containing boric acid capable of stably treating waste water containing boric acid for a long period of time for cement solidification.SOLUTION: The present invention comprises the steps: to insolubilize boric acid in a manner that precipitates the same contained in waste water as insoluble borate in a first tank; to store the waste water with the insolubilized boric acid in a second tank having an agitation mixer and to control pH of the waste water with the boric acid; to transfer the waste water with the insolubilized boric acid from the second tank to a dryer to separate the borate from the waste water with the insolubilized boric acid by drying; to clean the dryer by supplying cleaning water from a cleaning water tank and to transfer cleaning waste water containing residue of the borate to the second tank; and to pulverize the residue of the borate into fine particles by agitating with the agitation mixer in the second tank.
    • 要解决的问题:提供一种用于处理含有硼酸的废水的方法和装置,其能够长时间稳定地处理含有硼酸的废水用于水泥固化。 解决方案:本发明包括以下步骤:使硼酸以使第一罐中的不溶性硼酸盐沉淀在废水中所含的相同的方式不溶解; 将具有不溶硼酸的废水存储在具有搅拌混合器的第二罐中,并用硼酸控制废水的pH; 将不溶硼酸的废水从第二罐转移到干燥器中,通过干燥将硼酸盐与不溶的硼酸从废水中分离出来; 通过从清洁水箱中提供清洁水来清洁干衣机,并将含有硼酸盐残留物的清洁废水转移到第二罐; 并通过用第二罐中的搅拌混合器搅拌将硼酸盐的残余物粉碎成细颗粒。 版权所有(C)2012,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
    • JP2009162646A
    • 2009-07-23
    • JP2008001257
    • 2008-01-08
    • Toshiba Corp株式会社東芝
    • HARUGUCHI YOSHIKOTAKAHASHI RYOTAKANEKO MASAAKIYAMASHITA TAKEOSATO TATSUAKIMIKURA MICHITAKAARIMA YUKI
    • G21F9/30C08J11/14C08J11/16
    • Y02W30/704Y02W30/705
    • PROBLEM TO BE SOLVED: To provide a method for treating used ion-exchange resin which makes it possible to dispose of the resin more efficiently at lower costs than ever. SOLUTION: The ion-exchange group disabling treatment process of disabling ion-exchange groups is carried out for a used ion-exchange resin 1 (of a sulfonic acid base) adsorbing radionuclides 2. As to the ion-exchange group disabling treatment process; hydrolysis under a hydrothermal condition, alkali fusion by using a strong basic salt or reduction treatment is adopted. The ion-exchange group disabling treatment process desorbs the radionuclides 2 from the used ion-exchange resin 1. Then, a liquid for a reaction containing the used ion-exchange resin 1a in the state that the radionuclides 2 have desorbed and the desorbed radionuclides 2 is separated. COPYRIGHT: (C)2009,JPO&INPIT
    • 要解决的问题:提供一种处理使用的离子交换树脂的方法,其可以以比以往更低的成本更有效地处理树脂。 解决方案:对于吸附放射性核素2的使用的离子交换树脂1(磺酸基)的离子交换基团不能进行离子交换基团的残留处理过程。对于离子交换基团残留处理 处理; 在水热条件下水解,采用强碱性碱还原法进行碱熔融。 离子交换基团禁用处理工序从使用的离子交换树脂1中解吸放射性核素2.然后,在放射性核素2脱附的状态下,含有使用的离子交换树脂1a的反应用液体和解吸的放射性核素2 被分开。 版权所有(C)2009,JPO&INPIT
    • 36. 发明专利
    • Solidification processing method of radioactive waste
    • 放射性废物的固体加工方法
    • JP2007132787A
    • 2007-05-31
    • JP2005325900
    • 2005-11-10
    • Toshiba Corp株式会社東芝
    • MIYAMOTO MASAYASATO TATSUAKIHARUGUCHI YOSHIKOMIKURA MICHITAKAKOMATSUBARA MASARUSAKURAI JIRO
    • G21F9/30G21F9/16
    • PROBLEM TO BE SOLVED: To provide a solidification processing method of radioactive wastes, capable of securing soundness of a disposal site over a long time, by controlling or preventing the generation of gas from a cement solidified matter due to radiolysis, while the cement solidified matter is buried underground and control or inhibit the increase in pressure, inside a containment vessel buried underground for disposal.
      SOLUTION: The solidification processing method of radioactive waste comprising the steps of filling a containment vessel with a mixture containing a processing object matter containing radioactive wastes, a hydraulic inorganic solidifying material and water and solidifying the mixture to produce solidified matter comprises the solidification processing of filling the containment vessel with the mixture and solidifying the mixture to produce solidified matter, a drying process of heating and drying the solidified at a stage of uniaxial compression strength of not smaller than 1.5 MPa and not larger than 75% of a planned strength and the sealing process of putting a lid on the containment vessel and of sealing the vessel after the drying process.
      COPYRIGHT: (C)2007,JPO&INPIT
    • 解决的问题:为了提供能够通过控制或防止由于放射线分解从水泥固化物质产生气体而能够长时间确保处置场所的健全性的放射性废料的固化处理方法,而 水泥凝固物埋在地下,控制或抑制压力增加,埋藏在地下的安全壳内处置。 解决方案:放射性废物的固化处理方法包括以下步骤:用含有放射性废物的加工对象物,水硬性无机固化材料和水的混合物填充容纳容器并固化混合物以产生固化物质的步骤包括固化 处理用混合物填充容纳容器并固化混合物以产生固化物质,在单轴压缩强度不小于1.5MPa且不大于计划强度的75%的阶段加热和干燥固化的干燥过程 以及在密封容器上盖上盖子并在干燥过程之后密封容器的密封过程。 版权所有(C)2007,JPO&INPIT
    • 37. 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