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    • 1. 发明专利
    • Solidification disposal method for radioactive waste
    • 放射性废物固化处理方法
    • JP2007003393A
    • 2007-01-11
    • JP2005184863
    • 2005-06-24
    • Hitachi LtdKansai Electric Power Co Inc:The株式会社日立製作所関西電力株式会社
    • ASANO TAKASHINOSHITA KENJIKAWASAKI TORUKONDO YOSHIKAZUYAMAZAKI HIROTOHORIKAWA YOSHIHIKOHATSUOKA YOSHIMASAYASUDA TAKASHIHIGUCHI NATSUKO
    • G21F9/16G21F9/06
    • PROBLEM TO BE SOLVED: To provide a solidification disposal method for a radioactive waste provided with a procedure for determining within a proper range an amount of an alkaline earth metal compound and a material/compounding of a curing agent added to a radioactive waste liquid containing sulfate ion or the radioactive waste containing a soluble sulfate compound to bring a pH of water contacting with a solidified body into 12 or less and to bring a sulfate ion concentration into 200ppm or less.
      SOLUTION: The alkaline earth metal compound 7 is added to the radioactive waste in a drum can 4 to bring a molar amount of alkaline earth metal into 1.0 or more with respect to a molar amount of the sulfate ion contained in the radioactive waste, so as to prepare a mixture of a sulfate of a solidlike alkaline earth metal and a solution containing an alkali metal ion, and a silicon oxide compound 8 and blast furnace water granulation slag and/or fly ash 9 are added as the curing agent to the mixture to bring a molar amount into 1.2 or more with respect to a molar amount of the alkali metal contained in the radioactive waste, and is stirred by a stirrer 5 to be solidified.
      COPYRIGHT: (C)2007,JPO&INPIT
    • 要解决的问题:为了提供放射性废物的固化处理方法,其具有在适当范围内确定碱土金属化合物的量和添加到放射性废物中的固化剂的材料/配混的程序 含有硫酸根离子的液体或含有可溶性硫酸盐化合物的放射性废物使与固化体接触的水的pH达到12以下,并使硫酸根离子浓度达到200ppm以下。 解决方案:将碱土金属化合物7添加到鼓罐4中的放射性废物中,使碱土金属的摩尔量相对于放射性废物中所含的硫酸根离子的摩尔量为1.0以上 ,以制备固体状碱土金属的硫酸盐和含有碱金属离子的溶液和氧化硅化合物8和高炉水造粒渣和/或飞灰9的混合物作为固化剂加入到 所述混合物相对于放射性废物中所含的碱金属的摩尔量使摩尔量为1.2以上,并通过搅拌器5搅拌而固化。 版权所有(C)2007,JPO&INPIT
    • 2. 发明专利
    • Solidification treatment method of radioactive effluent
    • 放射性污染物的固化处理方法
    • JP2006258719A
    • 2006-09-28
    • JP2005079389
    • 2005-03-18
    • Hitachi LtdKansai Electric Power Co Inc:The株式会社日立製作所関西電力株式会社
    • KAWASAKI TORUKONDO YOSHIKAZUYAMAZAKI HIROTOASANO TAKASHINOSHITA KENJIHORIKAWA YOSHIHIKOHATSUOKA YOSHIMASAYASUDA TAKASHIHIGUCHI NATSUKO
    • G21F9/16G21F9/10
    • PROBLEM TO BE SOLVED: To provide a solidification treatment method of radioactive effluent for rapidly and accurately determining an optimum amount of added chemical even if the concentration of sodium sulfate changes tank by tank/with every effluent collection.
      SOLUTION: While controlling the liquid level by means of a sensor 102, the effluent in a tank 100 is put into a solidification container 101 by a determinate volume to find its weight by an instrument 103. The weight and the put-in volume are used to calculate the density of the effluent. A prescribed graph is referred to to estimate the concentration of sodium sulfate corresponding to the calculated density. Barium hydroxide whose volume corresponds to the estimated concentration of sulfuric acid is added from a tank 104 to a tank 100, thereby insolubilizing the sulfuric acid. In the process of insolubilization treatment, barium hydroxide is inputted in the sulfuric acid, which is kept at 60°C or more, and its effluent is kneaded. Since a solution after the insolubilization shows high pH, silicic acid which is a major constituent of silica fume is added thereto for reaction from a tank 105, thereby synthesizing sodium silicate (water glass) which is a solidifying material.
      COPYRIGHT: (C)2006,JPO&NCIPI
    • 要解决的问题:为了提供放射性流出物的凝固处理方法,即使硫酸钠的浓度通过罐/每个流出物收集罐改变罐,也可快速和准确地确定添加的化学品的最佳量。 解决方案:在通过传感器102控制液面的同时,将罐100中的流出物以一定的体积放入固化容器101中,以通过仪器103找到其重量。重量和放入 体积用于计算流出物的密度。 参考规定的图表来估计对应于计算密度的硫酸钠浓度。 将体积对应于硫酸的估计浓度的氢氧化钡从罐104加入到罐100中,从而使硫酸不溶解。 在不溶解处理的过程中,将氢氧化钡输入到保持在60℃以上的硫酸中,其流出物被捏合。 由于不溶解后的溶液显示高pH,所以加入作为硅灰的主要成分的硅酸从罐105反应,从而合成作为凝固材料的硅酸钠(水玻璃)。 版权所有(C)2006,JPO&NCIPI
    • 3. 发明专利
    • Radioactive waste solidification method and solidification device
    • 放射性废物固化方法和固化装置
    • JP2006258716A
    • 2006-09-28
    • JP2005079278
    • 2005-03-18
    • Hitachi LtdKansai Electric Power Co Inc:The株式会社日立製作所関西電力株式会社
    • KAWASAKI TORUKONDO YOSHIKAZUYAMAZAKI HIROTOASANO TAKASHINOSHITA KENJIHORIKAWA YOSHIHIKOHATSUOKA YOSHIMASAYASUDA TAKASHIHIGUCHI NATSUKO
    • G21F9/16G21F9/10
    • PROBLEM TO BE SOLVED: To efficiently solidify radioactive waste liquid containing sodium sulfate without allowing unreacting sulfate ions to remain therein, thereby obtaining a solidified body having high water resistance and extremely little affecting a buried artificial barrier.
      SOLUTION: In this radioactive waste liquid solidification method for solidifying radioactive waste liquid containing sodium sulfate, solidification procedure is divided into an insolubilization process for insolubilizing sulfate ions in the waste liquid while heating the waste liquid and a solidification process for solidifying the insolubilized waste liquid. Temperature variation is measured accompanying endothermic reaction of the waste liquid in the insolubilization process. Completion of the solidification process is determined based on the transition of temperature. After the completion of insolubilization, heating electric power is reduced and switching takes place to the solidification process (turning into water glass → polymerization solidification).
      COPYRIGHT: (C)2006,JPO&NCIPI
    • 要解决的问题:为了有效地固化含有硫酸钠的放射性废液,而不会残留硫酸根离子,从而获得具有高耐水性并且极少影响埋置的人造屏障的凝固体。 解决方案:在用于固化含有硫酸钠的放射性废液的放射性废液固化方法中,将固化步骤分为不溶解废液中的硫酸根离子同时加热废液的不溶化方法和固化不溶化的固化方法 废液。 随着不溶解过程中废液的吸热反应测量温度变化。 基于温度的转变来确定凝固过程的完成。 完成不溶化后,加热电力降低,凝固过程转化(变成水玻璃→聚合凝固)。 版权所有(C)2006,JPO&NCIPI
    • 4. 发明专利
    • Method for treating radioactive effluent solidification
    • 用于处理放射性水溶液固化的方法
    • JP2008102087A
    • 2008-05-01
    • JP2006286620
    • 2006-10-20
    • Hitachi-Ge Nuclear Energy LtdKansai Electric Power Co Inc:The日立Geニュークリア・エナジー株式会社関西電力株式会社
    • YAMAZAKI HIROTOASANO TAKASHIKAWASAKI TORUKONDO YOSHIKAZUHORIKAWA YOSHIHIKOHATSUOKA YOSHIMASAYASUDA TAKASHIHIGUCHI NATSUKO
    • G21F9/16
    • PROBLEM TO BE SOLVED: To provide a method for treating radioactive effluent solidification for making a solidified body employing an in-drum method and by solidifying a radioactive effluent containing sodium sulfate and having high radioactive concentration, wherein a solution resulting after the solid body is immersed in water that has a pH of 12 and a sulfate ion concentration that is not higher than a mortar equilibrium concentration.
      SOLUTION: Barium hydroxide 5 is added to a radioactive effluent 1 containing sodium sulfate so that the content of barium hydroxide becomes equivalent to or higher than the content of sodium sulfate in terms of mol, and a silicon oxide compound 6 and a water reducing agent 7 are added to a mixture of barium sulfate and an aqueous alkali solution, thus obtained, and are kneaded to produce water glass. A hardener 8 is added to a mixture of the water glass produced and barium sulfate prior to being subjected to the kneading and solidification treatment. A viscosity enabling solidification treatment by in-drum method can be obtained, by controlling a water/powder ratio and the quantity of the water reducing agent 7, wherein the ratio of total water/(total of silicon oxide compound 6 and hardener 8) is defined as the water/power ratio.
      COPYRIGHT: (C)2008,JPO&INPIT
    • 待解决的问题:提供一种处理放射性流出物固化的方法,用于制造使用滚筒内方法的凝固体并固化含有硫酸钠并具有高放射性浓度的放射性流出物,其中在固体之后产生的溶液 将身体浸入pH为12的水中,并且硫酸根离子浓度不高于砂浆平衡浓度。 解决方案:将氢氧化钡5加入到含有硫酸钠的放射性流出物1中,使氢氧化钡的含量等于或高于硫酸钠的含量,以摩尔计,氧化硅化合物6和水 将还原剂7加入到由此获得的硫酸钡和碱性水溶液的混合物中,并捏合以制备水玻璃。 在进行捏合和固化处理之前,将硬化剂8加入到生产的水玻璃和硫酸钡的混合物中。 通过控制水/粉末比例和减水剂7的量,可以获得通过内鼓方法进行固化处理的粘度,其中总水/(氧化硅化合物6和固化剂8的总量)的比率为 定义为水/功率比。 版权所有(C)2008,JPO&INPIT