-
公开(公告)号：US5158674A
公开(公告)日：1992-10-27
申请号：US625354
申请日：1990-12-11
申请人： Makoto Kikuchi , Shin Tamata , Masato Ohura , Toshio Sawa
发明人： Makoto Kikuchi , Shin Tamata , Masato Ohura , Toshio Sawa
CPC分类号： C02F1/44 , B01D61/36 , G21F9/12 , C02F2101/006
摘要： A radioactive waste liquid treatment apparatus according to the invention comprises an upstream-side filter unit having an inlet for radioactive waste liquid, and a downstream-side filter unit communicating with the upstream-side filter unit and having an outlet for filtrated liquid. Further, the upstream-side filter unit includes first filter member installed therein having active silica for removal of interfacial active agents and oil, whereas the downstream-side filter unit includes second filter member installed therein, and this second filter member has a vapor permeable membrane.
摘要翻译： 根据本发明的放射性废液处理装置包括具有用于放射性废液的入口的上游侧过滤器单元和与上游侧过滤器单元连通并具有用于过滤液体的出口的下游侧过滤器单元。 此外，上游侧过滤器单元包括安装在其中的第一过滤器构件，其具有用于除去界面活性剂和油的活性二氧化硅，而下游侧过滤器单元包括安装在其中的第二过滤器构件，并且该第二过滤构件具有蒸气透过膜 。
-
公开(公告)号：US5143654A
公开(公告)日：1992-09-01
申请号：US581904
申请日：1990-09-13
申请人： Makoto Kikuchi , Masato Ohura , Shin Tamata , Koichi Chino , Kiyomi Funabashi
发明人： Makoto Kikuchi , Masato Ohura , Shin Tamata , Koichi Chino , Kiyomi Funabashi
摘要： A method of solidifying a radioactive waste of an atomic power plant, for example, begins with concentrating the liquid waste to powder or pellet form to reduce its volume. Prior to reducing its volume, an estimation is made of what the concentration will be once the liquid waste is converted into powdered or pelletized form. The powdered or pelletized waste is charged into a container, and a solidifying agent is poured over the contents to form a solidified body. The solidifying agent is prepared to have a desired coefficient of distribution that is determined in accordance with the estimated concentration of the reduced volume solidified waste so that the amount of leaching of the solidified body that is produced will be less than or equal to a predetermined value, such as the known value of leaching for a conventional cement-solidified waste that is not processed to reduce its volume before being solidified.
-
3.发明授权
公开(公告)号：US5498828A
公开(公告)日：1996-03-12
申请号：US34885
申请日：1993-03-19
申请人： Masami Matsuda , Takashi Nishi , Makoto Kikuchi , Tatsuo Izumida , Shin Tamata , Yoshimasa Kiuchi
发明人： Masami Matsuda , Takashi Nishi , Makoto Kikuchi , Tatsuo Izumida , Shin Tamata , Yoshimasa Kiuchi
摘要： An object of the present invention is to improve retainability (distribution coefficient) for C-14 of a radioactive waste solidified body. The waste is solidified with a solidification agent containing a soluble substance which yields an insoluble substance by a reaction with carbonic ions, insoluble carbonates, or a mixture of the above substances. And, as for a pre-treatment, the soluble substance which yields an insoluble substance by a reaction with carbonic ions is previously reacted with liquid waste, and subsequently the solidification is performed. The retainability (distribution coefficient) for C-14 of the solidified body of the waste increases about one order.
摘要翻译： 本发明的目的在于提高放射性废物凝固体的C-14的保持性（分配系数）。 废物通过含有可溶性物质的凝固剂固化，通过与碳酸离子，不溶性碳酸酯或上述物质的混合物的反应产生不溶性物质。 并且，对于预处理，通过与碳离子反应产生不溶性物质的可溶性物质预先与废液反应，随后进行固化。 废物凝固体C-14的保留性（分布系数）大约增加一个数量级。
-
公开(公告)号：US4793947A
公开(公告)日：1988-12-27
申请号：US852821
申请日：1986-04-16
申请人： Tatsuo Izumida , Hideo Yusa , Kiyomi Funabashi , Makoto Kikuchi , Shin Tamata
发明人： Tatsuo Izumida , Hideo Yusa , Kiyomi Funabashi , Makoto Kikuchi , Shin Tamata
CPC分类号： G21F9/162
摘要： The present invention relates to a method and an apparatus for producing a waste package of radioactive waste containing particles of radioactive waste material of low modulus of elasticity, particles of radioactive waste material of high modulus of elasticity, and a solidifying agent in which the particles of radioactive waste material of low modulus of elasticity and the particles of radioactive waste material of high modulus of elasticity are fixed in an almost uniformly dispersed state. According to this invention, the radioactive waste generated from nuclear power plants can be greatly reduced in volume and also a waste package of radioactive waste with high strength and excellent water resistance can be obtained.
摘要翻译： 本发明涉及一种生产含有低弹性模量的放射性废料颗粒，高弹性模量的放射性废料颗粒和固化剂的放射性废物废物包装方法和装置， 低弹性模量的放射性废料和高弹性模量的放射性废料颗粒以几乎均匀分散的状态固定。 根据本发明，可以大大减少核电站产生的放射性废物的体积，并且还可以获得具有高强度和优异的耐水性的放射性废物的废物包装。
-
公开(公告)号：US4628837A
公开(公告)日：1986-12-16
申请号：US677992
申请日：1984-12-04
申请人： Kazuhide Mori , Shin Tamata , Makoto Kikuchi , Masami Matsuda , Yoshiyuki Aoyama
发明人： Kazuhide Mori , Shin Tamata , Makoto Kikuchi , Masami Matsuda , Yoshiyuki Aoyama
CPC分类号： G21F9/32
摘要： In a method of processing radioactive spent ion exchange resin, the spent ion exchange resin is pyrolyzed in an inert atmosphere and harmful decomposition gas such as sulfur and nitrogen compounds generated during pyrolysis is separated. Next, the spent ion exchange resin is pyrolyzed in oxidizing atmosphere and harmless gases such as carbon dioxide and water vapor gases are separated. It is preferred that a transition metal as a catalyst be adsorbed through ion exchange into spent cation exchange resin, and an anionic atom group containing a transition metal as a catalyst be adsorbed through ion exchange into spent anion exchange, before both of the pyrolysis steps. The pyrolysis is carried out at two atmosphere stages, and the harmful and harmless gases are decomposed separately. The pyrolysis in both of pyrolysis steps is effected at a temperature in the range of from 240.degree. to 420.degree. C. The proportions of the sulfur and nitrogen compounds in spent ion exchange resin after pyrolysis, and also the processing volume of the spent ion exchange resin can be reduced. And scattering of radioactive substances can be prevented. By adding a catalyst to the spent ion exchange resin, pyrolysis is carried out at a low temperature.
摘要翻译： 在处理放射性废离子交换树脂的方法中，废弃离子交换树脂在惰性气氛中热解，分解在热解过程中产生的有害的分解气体如硫和氮化合物。 接下来，用过的离子交换树脂在氧化气氛中热解，分离无害气体如二氧化碳和水蒸气。 优选的是，作为催化剂的过渡金属通过离子交换吸附到废阳离子交换树脂中，并且在两个热解步骤之前，通过离子交换将含有过渡金属的阴离子原子团吸附到废阴离子交换中。 热解在两个大气阶段进行，有害和无害气体分开分解。 在两个热解步骤中的热解在240〜420℃的温度范围内进行。热解后废离子交换树脂中的硫和氮化合物的比例以及废离子交换的处理体积 树脂可以减少。 可以防止放射性物质的散射。 通过向废离子交换树脂中加入催化剂，在低温下进行热解。
-
6.发明授权Method for solidification of waste, and apparatus, waste form, and solidifying material therefor 失效废弃物固化方法，装置，废物形式及固化材料
公开(公告)号：US5463171A
公开(公告)日：1995-10-31
申请号：US123359
申请日：1993-09-17
申请人： Takashi Nishi , Masami Matsuda , Kenji Noshita , Makoto Kikuchi , Tatsuo Izumida , Shin Tamata , Yoshimasa Kiuchi
发明人： Takashi Nishi , Masami Matsuda , Kenji Noshita , Makoto Kikuchi , Tatsuo Izumida , Shin Tamata , Yoshimasa Kiuchi
摘要： Objective of the present invention is to provide a preferable solidified body ensuring performance of artificial barrier in a solidifying process for incombustible miscellaneous solid waste and other wastes such as calcined ashes by preventing generation of hydrogen gas by a reaction of amphoteric metal included in the waste with solidifying materials.In order to suppress the reaction of the amphoteric metal with the solidifying materials, any one or arbitrary plurality of the following three means are provided in the solidifying materials;(1) A means for forming protection film on surface of the amphoteric metal,(2) A means for enhancing hydration reaction of cement,(3) A means for reducing basicity of the solidifying materials.In accordance with the present invention, a preferable solidified body can be obtained by a simple and easy method which does not necessitate separation and pre-treatment of the waste.
摘要翻译： 本发明的目的是提供一种优选的凝固体，其通过防止由废弃物中包含的两性金属的反应产生氢气，从而确保在不可燃杂项固体废物和其它废物如煅烧灰分的固化过程中的人造阻挡层的性能， 凝固材料。 为了抑制两性金属与凝固材料的反应，在固化材料中设置任意多种以下三种手段; （1）两性金属表面形成保护膜的方法，（2）增强水泥水化反应的手段，（3）降低固化物的碱度的手段。 根据本发明，可以通过简单且容易的方法获得优选的固化体，该方法不需要废物的分离和预处理。
-
公开(公告)号：US4654172A
公开(公告)日：1987-03-31
申请号：US613194
申请日：1984-05-23
申请人： Masami Matsuda , Yoshiyuki Aoyama , Fumio Kawamura , Hideo Yusa , Makoto Kikuchi , Shin Tamata , Susumu Horiuchi
发明人： Masami Matsuda , Yoshiyuki Aoyama , Fumio Kawamura , Hideo Yusa , Makoto Kikuchi , Shin Tamata , Susumu Horiuchi
CPC分类号： G21F9/14 , Y10S159/12
摘要： A method of processing radioactive waste resin by pyrolyzing radioactive waste ion exchange resin generated in a nuclear plant such as a nuclear power station. First, the ion exchange resin is pyrolyzed at a low temperature, and the resulting decomposition gas is separated. Second, the ion exchange resin at a high temperature, and the resulting decomposition gas is separated. Finally, the residue of the ion exchange resin is hot-pressed into a molded article.
摘要翻译： 通过热解核电厂如核电站产生的放射性废物离子交换树脂来处理放射性废弃树脂的方法。 首先，将离子交换树脂在低温下热解，分解气体。 第二，高温下的离子交换树脂，分解出的分解气体。 最后，将离子交换树脂的残余物热压成模制品。
-
公开(公告)号：US4648990A
公开(公告)日：1987-03-10
申请号：US681907
申请日：1984-12-14
申请人： Naohito Uetake , Fumio Kawamura , Hideo Yusa , Makoto Kikuchi , Shin Tamata
发明人： Naohito Uetake , Fumio Kawamura , Hideo Yusa , Makoto Kikuchi , Shin Tamata
摘要： YThis invention concerns solidification products capable of immobilizing radioactive wastes containing water soluble solid components stably for a long period of time, as well as a process for producing the same, in which radioactive wastes are immobilized with an alkaline earth metal silicate compound and the alkaline earth metal silicate compound intakes the water content in the solidifying agent as the bound water to or a hydrate. High temperature and high humidity condition has been found to be necessary upon curing in order to take the water content as the bound water. This invention can provide solidified wastes with less development of detects such as open pores or cracks.
摘要翻译： Y本发明涉及能够固定长时间稳定地含有水溶性固体成分的放射性废物的固化物及其制造方法，其中放射性废物用碱土金属硅酸盐化合物和碱土金属固定 金属硅酸盐化合物将固化剂中的水含量作为结合水或水合物。 已经发现在固化时需要高温和高湿度条件以将含水量作为结合水。 本发明可以提供具有较少发展的凝固废物，例如开孔或裂纹。
-
公开(公告)号：US5489737A
公开(公告)日：1996-02-06
申请号：US924482
申请日：1992-08-04
申请人： Tsutomu Baba , Masami Matsuda , Takashi Nishi , Koichi Chino , Makoto Kikuchi , Shin Tamata
发明人： Tsutomu Baba , Masami Matsuda , Takashi Nishi , Koichi Chino , Makoto Kikuchi , Shin Tamata
摘要： A processing system for radioactive waste is composed of an adjusting tank having a sampling port, a solidification processing system, and a package inspection apparatus, and a package, of which inventory per a package has been exactly grasped, is prepared by solidification of the waste with the processing system after determining radioactivity of the waste by measurement before the solidifying process.In accordance with the present invention, data on radioactivity before and after preparation of package of waste become clear, and management of each package at transportation and intermediate storage of the packages is facilitated.
摘要翻译： 放射性废物处理系统由具有采样口，凝固处理系统和包装检查装置的调节罐组成，其中包装已经被精确地夹在其中，通过废物的固化来制备 处理系统在固化过程之前通过测量确定废物的放射性。 根据本发明，废弃物包装前后的放射性数据变得清楚，并且便于包装运输和中间储存时的每个包装的管理。
-
10.发明授权Process for treating radioactive liquid waste containing sodium borate and solidified radioactive waste 失效处理含硼酸钠和固化放射性废物的放射性废液处理方法
公开(公告)号：US4931222A
公开(公告)日：1990-06-05
申请号：US384888
申请日：1989-07-24
申请人： Tsutomu Baba , Fumio Kawamura , Koichi Chino , Kiroyuki Tsuchiya , Makoto Kikuchi , Shin Tamata
发明人： Tsutomu Baba , Fumio Kawamura , Koichi Chino , Kiroyuki Tsuchiya , Makoto Kikuchi , Shin Tamata
CPC分类号： G21F9/14 , Y10S159/12
摘要： The present invention provides drying and pulverization of a radioactive liquid waste containing sodium borate as a main component by heating, where the liquid waste is heated, dried and pulverized to substantially crystalline, homogeneous powder of sodium borate while suppressing occurrence of a foaming phenomenon of the powder. The susbtantially crystalline powder is obtained by heating, drying and pulverizing the liquid waste at a temperature outside the temperature range where the salt powder takes an amorphous state in the course of releasing water of crystallization from the salt powder. In the drying and pulverization of a liquid waste containing sodium borate by a thin film evaporator, occurrence of the foaming phenomenon can be suppressed by maintaining the temperature on the heat transfer surface of the evaporator at a temperature lower than 150.degree. C.
摘要翻译： 本发明通过加热干燥和粉碎含有硼酸钠作为主要成分的放射性废液，其中将废液加热，干燥并粉碎成基本上结晶的均匀的硼酸钠粉末，同时抑制发泡现象 粉末。 通过在从盐粉中释放结晶水的过程中盐粉呈非晶状态的温度以外的温度下加热，干燥和粉碎废液而获得悬浮结晶性粉末。 在通过薄膜蒸发器干燥和粉碎含有硼酸钠的废液时，通过将蒸发器的传热表面上的温度保持在低于150℃的温度，可以抑制发泡现象的发生。
-
-
-
-
-
-
-
-
-
搜索结果
142 条记录 (耗时 0.022 秒)
