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    • 12. 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
    • 13. 发明专利
    • Method and device for processing spent ion exchange resin
    • 用于处理离子交换树脂的方法和装置
    • JP2011214971A
    • 2011-10-27
    • JP2010082861
    • 2010-03-31
    • Toshiba Corp株式会社東芝
    • HARUGUCHI YOSHIKOYASUI AYAKAYAMASHITA TAKEOKANEKO MASAAKI
    • G21F9/30G21F9/16
    • PROBLEM TO BE SOLVED: To provide a processing method and device of a spent ion exchange resin capable of disposing the spent ion exchange resin more inexpensively and efficiently than hitherto.SOLUTION: This processing method of a spent ion exchange resin for processing the spent ion exchange resin on which a radioactive material is adsorbed includes: an ion exchange group deactivation processing step for eliminating the radioactive material from the spent ion exchange resin, by deactivating an ion exchange group which is a radioactive material adsorption portion of the spent ion exchange resin by an oxidation reaction using an oxidizing agent; a separation step for separating the spent ion exchange resin from which the radioactive material is eliminated from the radioactive material; and a volume reduction step for reducing the volume of the spent ion exchange resin from which the radioactive material is eliminated.
    • 要解决的问题:提供一种能够比迄今为止更廉价和有效地处理废离子交换树脂的废离子交换树脂的处理方法和装置。解决方案:用于处理废离子交换的废离子交换树脂的处理方法 吸附有放射性物质的树脂包括:离子交换基团失活加工步骤,用于通过使废离子交换树脂的放射性物质吸附部分的离子交换基团失活,从废离子交换树脂中除去放射性物质 使用氧化剂的氧化反应; 分离步骤,用于从放射性物质中分离消除放射性物质的废离子交换树脂; 以及用于减少消除放射性物质的废离子交换树脂的体积的体积减小步骤。
    • 19. 发明专利
    • Method and apparatus for processing spent fuel aggregate
    • 用于处理燃料燃料的方法和装置
    • JP2013160601A
    • 2013-08-19
    • JP2012021904
    • 2012-02-03
    • Toshiba Corp株式会社東芝
    • OKABE HIROSHIYAMASHITA TAKEOHARUGUCHI YOSHIKOHOTTA KOJIOMURA TSUNEOOSATO TETSUO
    • G21C19/34G21C19/37G21F9/30
    • PROBLEM TO BE SOLVED: To collect volatile radioactive nuclides generated in a spent fuel aggregate processing step by a simple method and a simple apparatus.SOLUTION: A spent fuel aggregate is sheared or cut off and applied to dissolving processing (S1), separation processing (S2) of at least hulls and end pieces is performed from hull/end pieces obtained from the spent fuel aggregate, and then drying processing (S4) is performed for at least the hulls and the end pieces filled in a predetermined container by filling processing (S3). After the drying processing, compression processing (S5) is performed for at least the hulls and the end pieces filled in the container. Then, off-gas generated at least in the separation processing, the filling processing, the drying processing, and the compression processing is collected (S6).
    • 要解决的问题:通过简单的方法和简单的装置收集在乏燃料骨料加工步骤中产生的挥发性放射性核素。解决方案:将废燃料骨料剪切或切割并应用于溶解处理(S1),分离处理 S2)至少由从乏燃料骨料获得的船体/端部件进行船体和端部件的干燥处理(S4),然后通过填充处理(至少)对装载在预定容器中的船体和端部进行干燥处理(S4) S3)。 在干燥处理之后,至少对装载在容器中的船体和端部进行压缩处理(S5)。 然后,收集至少在分离处理,填充处理,干燥处理和压缩处理中产生的废气(S6)。
    • 20. 发明专利
    • Radioactive waste solidification method
    • 放射性废物固化方法
    • JP2010261907A
    • 2010-11-18
    • JP2009114778
    • 2009-05-11
    • Toshiba Aitekku KkToshiba Corp東芝アイテック株式会社株式会社東芝
    • SATO TATSUAKISHOJI YUICHIYAMASHITA TAKEOKOMATSUBARA MASARUYASUMURA KEIJIRO
    • G21F9/30G21F9/16
    • PROBLEM TO BE SOLVED: To provide a radioactive waste solidification method for satisfactorily solidifying incineration ash of a relatively high radiation dose, with cement as the solidifying material. SOLUTION: The radioactive waste solidification and disposal method uses a kneading and solidifying container having a powder material cast port and a liquid material cast port; inputs the powder radioactive waste, kneading water, cement, and a setting accelerator into the kneading and solidifying container via the powder material cast port and the liquid material cast port to knead them; and then solidify them in the kneading and solidifying container. The radioactive waste contains one or more kinds of heavy metals selected from among zinc and lead. The number of moles of the amount of the setting accelerator cast to the kneading and solidifying container is not less than 2.1 times the number of moles of the heavy metals of the radioactive waste cast with respect to the kneading and solidifying container. COPYRIGHT: (C)2011,JPO&INPIT
    • 要解决的问题:提供放射性废物固化方法,以令人满意地凝固相对较高辐射剂量的焚化灰,其中以水泥作为凝固材料。 解决方案:放射性废物固化处理方法使用具有粉末铸造口和液体铸造口的捏合固化容器; 将粉末放射性废物,捏合水,水泥和凝固促进剂经由粉末铸造口和液体铸造口输入捏合固化容器中以进行捏合; 然后将其固化在捏合和固化容器中。 放射性废物含有选自锌和铅的一种或多种重金属。 添加到捏合固化容器中的凝固促进剂的摩尔数不小于相对于捏合固化容器的放射性废物铸造重金属的摩尔数的2.1倍。 版权所有(C)2011,JPO&INPIT