公开(公告)号：US5028298A

公开(公告)日：1991-07-02

申请号：US273513

申请日：1988-11-04

申请人： Tsutomu Baba ,  Koichi Chino ,  Shunsuke Uchida ,  Toshio Sawa ,  Makoto Kikuchi

发明人： Tsutomu Baba ,  Koichi Chino ,  Shunsuke Uchida ,  Toshio Sawa ,  Makoto Kikuchi

IPC分类号： G21F9/08 ,  B01D1/30 ,  B01D19/00 ,  B01D46/00 ,  C02F1/04 ,  G21F9/00

CPC分类号： B01D1/305 ,  B01D19/0031 ,  C02F1/048 ,  Y10S159/12 ,  Y10S159/27 ,  Y10S159/28 ,  Y10S203/16

摘要： The present invention relates to a technique of concentrating waste water whereby the water content of the waste water is removed with a high decontamination factor, employs a porous membrane having a property allowing gas such as steam to permeate but not allowing a liquid such as water to do, as a membrane for concentrating the waste water, and adopts a method wherein the waste water is turned into a vapor flow and this vapor flow is made to contact the porous membrane so as for the waste water to be concentrated on the occasion when the waste water is to be concentrated by means of this porous membrane. By turning the waste water into the vapor flow, most of various metal ions, a surfactant, etc. existing in the waste water are separated from the vapor flow. Mist, metal ions in the mist and others contained in the vapor flow are removed by the aforesaid porous membrane from the steam while permeating the same. This enables the disposal of the waste water with a high decontamination factor, for a long duration and in a stable manner. When this technique of concentrating waste water is adapted to a plant for disposal of waste water of high electroconductivity produced from a nuclear power station, for instance, various tanks, a demineralizer, ion-exchange resin, etc. provided on the downstream of a concentrator are dispensed with, and thus the plant for disposal can be simplified to a large extent.

摘要翻译： PCT No.PCT / JP88 / 00245 Sec。 371日期：1988年11月4日 102（e）日期1988年11月4日PCT PCT。 出版物WO88 / 06914 日本公开日1988年9月22日。本发明涉及一种浓缩废水的技术，其中废水的含水量以高净化因子除去，采用具有允许诸如蒸汽的气体渗透但不允许的性质的多孔膜 允许诸如水的液体作为用于浓缩废水的膜，并且采用其中废水变成蒸汽流的方法，并使该蒸汽流与多孔膜接触，以使废水达到 集中在废水通过该多孔膜浓缩的场合。 通过将废水转化为蒸汽流，存在于废水中的大多数各种金属离子，表面活性剂等与蒸汽流分离。 雾中的金属离子和包含在蒸气流中的其它物质被透过前述多孔膜从蒸汽中除去。 这样可以长时间和稳定地处理具有高去污因子的废水。 当这种将废水浓缩的技术适用于处理从核电站产生的高导电性废水的设备，例如设置在浓缩器下游的各种罐，脱盐装置，离子交换树脂等 可以在很大程度上简化处理设备。

公开(公告)号：US5481061A

公开(公告)日：1996-01-02

申请号：US141541

申请日：1993-10-27

申请人： Kiyomi Funabashi ,  Koichi Chino ,  Osamu Kuriyama ,  Tsutomu Baba ,  Shunsuke Uchida ,  Makoto Kikuchi

发明人： Kiyomi Funabashi ,  Koichi Chino ,  Osamu Kuriyama ,  Tsutomu Baba ,  Shunsuke Uchida ,  Makoto Kikuchi

IPC分类号： C04B28/02 ,  G21F9/16 ,  G21F9/30 ,  G21F9/00

CPC分类号： C04B28/02 ,  G21F9/16 ,  G21F9/165 ,  G21F9/304

摘要： The present invention relates to a method of solidifying radioactive waste with cement, comprising forming a mixture comprising water, a hydrophilic material and cement substantially non-shrinkable or expansible with respect to volume change upon hardening, mixing said mixture with the radioactive waste, followed by hardening to form a solid body.The present invention enables the formation of a compact solid body having voids, such as capillary voids, of reduced volume, which makes it possible to reduce the leaching rate of hazardous materials. Further, since no shrinkage accompanies hardening, no tensile stress occurs in the cement surrounding minute waste particles within the hardened material, thereby enabling a decrease in the strength of the solid body to be minimized. This in turn enables an increase in the amount of packing of waste. Prior addition of a hydrophilic material enables the cement fluidity before hardening to be maintained even after complete absorption of water by a water absorptive waste. This is extremely advantageous in carrying out hardening.

摘要翻译： 本发明涉及一种用水泥固化放射性废物的方法，包括形成水，亲水材料和水泥在混合物硬化后基本上不可收缩或可膨胀的混合物，将所述混合物与放射性废物混合，然后 硬化形成固体。 本发明能够形成具有减小体积的诸如毛细管空隙的空隙的紧凑的固体，这使得可以降低有害材料的浸出率。 此外，由于没有收缩伴随硬化，所以在硬化材料内的微小废弃颗粒周围的水泥中不产生拉伸应力，从而能够使固体的强度降低到最小。 这又可以增加废物的包装量。 亲水性材料的先前添加使得即使在通过吸水性废物完全吸收水之后，硬化前的水泥流动性仍能保持。 这在进行硬化方面是非常有利的。

公开(公告)号：US5256338A

公开(公告)日：1993-10-26

申请号：US796829

申请日：1991-11-25

申请人： Takashi Nishi ,  Masami Matsuda ,  Itaru Komori ,  Tsutomu Baba ,  Koichi Chino ,  Takashi Ikeda ,  Makoto Kikuchi

发明人： Takashi Nishi ,  Masami Matsuda ,  Itaru Komori ,  Tsutomu Baba ,  Koichi Chino ,  Takashi Ikeda ,  Makoto Kikuchi

IPC分类号： G21F9/12 ,  G21F9/00 ,  G21F9/16 ,  G21F9/30 ,  G21F9/34 ,  G21F9/36

CPC分类号： G21F9/34 ,  G21F9/008 ,  G21F9/304

摘要： According to the present invention, a fibrous material having a property to adsorb radioactive nuclides in the form of ion or molecule onto its surface is added to a cement type hydraulic solidifying material used for a solidifying material, a waste container, a structure in disposal site and a back-filling material used for production of a waste form of radioactive wastes, whereby improvement of long-term endurance of the waste form, the structure and the like and diminishment of leaching of radioactivity from the waste form and the like can be simultaneously attained.

摘要翻译： 根据本发明，将具有将离子或分子形式的放射性核素吸附到其表面上的性质的纤维材料被添加到用于固化材料，废物容器，处置场所中的结构的水泥型液压固化材料 以及用于生产废弃形式的放射性废物的补充填充材料，由此可以同时改善废物形式，结构等的长期耐久性和放射性从废物形式等的浸出的减少 达到了

公开(公告)号：US5202062A

公开(公告)日：1993-04-13

申请号：US660997

申请日：1991-02-26

申请人： Tsutomu Baba ,  Koichi Chino ,  Masami Matsuda ,  Takashi Nishi ,  Kiyomi Funabashi ,  Takashi Ikeda ,  Akira Sasahiro ,  Makoto Kikuchi ,  Shin Tamada

发明人： Tsutomu Baba ,  Koichi Chino ,  Masami Matsuda ,  Takashi Nishi ,  Kiyomi Funabashi ,  Takashi Ikeda ,  Akira Sasahiro ,  Makoto Kikuchi ,  Shin Tamada

IPC分类号： G21F9/00 ,  G21F9/06 ,  G21F9/16

CPC分类号： G21F9/008 ,  G21F9/06 ,  G21F9/162

摘要： The present invention adds carbonates or chlorides of alkaline earth metals to the radioactive wastes containing sodium sulfate and subjects sulfate group in the radioactive wastes to reduction treatment, thereby converts the sulfate group into sulfides of alkaline earth metals which are chemically stable substances while suppressing SOx generation, and solidifies the radioactive wastes stably for an extended period of time by applying to the converted radioactive wastes solidifying treatment.

摘要翻译： 本发明将碱土金属的碳酸盐或氯化物添加到放射性废物中含有硫酸钠和硫酸根的放射性废物进行还原处理，从而将硫酸盐转化为化学稳定物质的碱土金属硫化物，同时抑制SOx产生 并通过应用于转化的放射性废物固化处理，将放射性废物稳定地长时间固化。

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

IPC分类号： G21F9/00 ,  G21F9/06 ,  G21F9/16 ,  G21F9/30

CPC分类号： G21F9/16 ,  G21F9/008 ,  G21F9/301

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。

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

IPC分类号： G21F9/08 ,  G21F9/00 ,  G21F9/14 ,  G21F9/16

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。

公开(公告)号：US5114622A

公开(公告)日：1992-05-19

申请号：US449917

申请日：1989-12-14

申请人： Kiyomi Funabashi ,  Osamu Kuriyama ,  Koichi Chino ,  Tsutomu Baba ,  Takashi Nishi ,  Makoto Kikuchi

发明人： Kiyomi Funabashi ,  Osamu Kuriyama ,  Koichi Chino ,  Tsutomu Baba ,  Takashi Nishi ,  Makoto Kikuchi

IPC分类号： G21F9/16 ,  G21F9/00 ,  G21F9/30

CPC分类号： G21F9/304

摘要： The present invention relates to a method of cementing a radioactive waste and a cemented body thereof which are less liable to bring about radioactivity leakage for a long period of time and suitable for disposal of cemented bodies of radioactive wastes in the land.The radioactivity leakage from a cemented body of a radioactive waste occurs due to the presence of the voids within the cemented body, and these voids are formed during hardening of the cemented body or by leaching of a soluble component from the cemented body during immersion in water.In the present invention, in order to minimize the amount of radioactivity leakage, the fraction of fine voids (1 .mu.m or less) is limited to 20% by volume or less. In order to attain such a void fraction, operating conditions, such as water to cement ratio, hardening time of a mixture of a solidifying material with a waste, and addition of an organic polymer, are properly determined.Further, in order to prevent formation of a soluble component, i.e., Ca(OH).sub.2, the CaO content of the cement is limited to not less than 0.62.times.C.sub.SiO.sbsb.2 +0.27.times.C.sub.Al.sbsb.2.sub.O.sbsb.3 and not more than 1.87.times.C.sub.SiO.sbsb.2 +2.20.times.C.sub.Al.sbsb.2.sub.O.sbsb.3, wherein C.sub.SiO.sbsb.2 is the silicon content (% by weight) in terms of SiO.sub.2 and C.sub.Al.sbsb.2.sub.O.sbsb.3 is the aluminum content (% by weight) in terms of Al.sub.2 O.sub.3.

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

IPC分类号： G21F9/16 ,  G21F9/00 ,  G21F9/14 ,  G21F9/30 ,  G21F9/36

CPC分类号： G21F9/14 ,  G21F9/008 ,  G21F9/302 ,  G21F9/304

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.

公开(公告)号：US4361505A

公开(公告)日：1982-11-30

申请号：US117089

申请日：1980-01-31

申请人： Makoto Kikuchi ,  Koichi Chino ,  Fumio Kawamura ,  Hideo Yusa

发明人： Makoto Kikuchi ,  Koichi Chino ,  Fumio Kawamura ,  Hideo Yusa

IPC分类号： C02F1/08 ,  C02F11/00 ,  G21F9/00 ,  G21F9/08 ,  G21F9/16 ,  G21F9/30

CPC分类号： G21F9/167

摘要： N-.beta.-(aminoethyl)-.gamma.-aminopropyltrimethoxysilane [NH.sub.2 (CH.sub.2).sub.2 NH(CH.sub.2).sub.3 Si(OCH.sub.3).sub.3 ] as a silane coupling agent and SiO.sub.(2-x) (ONa).sub.x/2 (OH).sub.x/2 as colloidal silica are mixed into a radioactive liquid waste containing sodium sulfate as a main component, coming from a boiling water-type, nuclear power plant as an effluent. The resulting mixed radioactive liquid waste is supplied into a vessel provided with a rotating shaft with blades. The rotating shaft is revolved while heating the radioactive liquid waste in the vessel, thereby making the radioactive liquid waste into powder. The resulting powder containing the silane coupling agent and the colloidal silica is shaped into pellets by a pelletizer. The pellets having a low hygroscopicity and a high strength are obtained.

摘要翻译： 作为硅烷偶联剂和SiO（2-x）（ONa）x / 2（OH）x / 2的N-β-（氨基乙基）-γ-氨基丙基三甲氧基硅烷[NH2（CH2）2NH（CH2）3Si（OCH3） 作为胶体二氧化硅作为主要成分混入含有硫酸钠的放射性废液中，作为流出物来自沸水型核电厂。 所得到的混合放射性废液被供给到具有带叶片的旋转轴的容器中。 旋转轴在加热容器内的放射性废液的同时旋转，从而使放射性废液成粉末。 所得到的含有硅烷偶联剂和胶体二氧化硅的粉末通过造粒机成形为颗粒。 获得具有低吸湿性和高强度的颗粒。

公开(公告)号：US4268409A

公开(公告)日：1981-05-19

申请号：US58174

申请日：1979-07-17

申请人： Eiichi Ga ,  Koichi Chino ,  Makoto Kikuchi ,  Akira Oda ,  Susumu Horiuchi

发明人： Eiichi Ga ,  Koichi Chino ,  Makoto Kikuchi ,  Akira Oda ,  Susumu Horiuchi

IPC分类号： G21F9/30 ,  G21F9/08

CPC分类号： G21F9/30

摘要： An aqueous solution containing granular ion exchange resin and filter aid as a radioactive waste generated from a nuclear power plant is supplied to the casing of a centrifugal film dryer, which comprises a casing, a rotating shaft inserted in the casing, rotating blades fixed to the rotating shaft within the casing, and a heating means for heating the wall surface of the casing. The aqueous solution flows down along the heated inside wall of the casing while the rotating shaft is rotated. Water of the aqueous solution is evaporated, while the granular ion exchange resin and the filter aid are turned into powder by the action of rotating blades in rotation. The powder is led to a pelletizer, and shaped into pellets. The pellets are filled in a drum, and asphalt is then filled in the drum. After the solidification of the asphalt, the drum is tightly sealed.

摘要翻译： 将含有粒状离子交换树脂的水溶液和作为放射性废物的核动力装置产生的助滤剂供给到离心式薄膜干燥机的壳体中，该离心式薄膜干燥机包括壳体，插入壳体中的旋转轴，固定在壳体上的旋转叶片 壳体内的旋转轴，以及用于加热壳体壁面的加热装置。 当旋转轴旋转时，水溶液沿壳体的加热内壁向下流动。 水溶液的水蒸发，同时粒状离子交换树脂和助滤剂通过旋转叶片的作用变成粉末。 将粉末导入造粒机，并成型成颗粒。 将颗粒填充在滚筒中，然后将沥青填充在滚筒中。 在沥青固化后，滚筒密封。