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

IPC分类号： G21F9/10 ,  G21F9/16 ,  G21F9/30 ,  A62D3/00 ,  G21F9/00

CPC分类号： G21F9/162 ,  G21F9/302

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：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

IPC分类号： B09B3/00 ,  G21F9/00 ,  G21F9/30

CPC分类号： G21F9/008 ,  G21F9/304

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：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：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

IPC分类号： G21F9/30 ,  G21F9/32 ,  F23G7/00

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。

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

IPC分类号： G21F9/30 ,  G21F9/00 ,  G21F9/14 ,  G21F9/32 ,  G21F9/16

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：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：US06800196B2

公开(公告)日：2004-10-05

申请号：US10029260

申请日：2001-12-28

申请人： Toshiaki Matsuo ,  Takashi Nishi ,  Takayuki Matsumoto ,  Masami Matsuda ,  Atsushi Yukita

发明人： Toshiaki Matsuo ,  Takashi Nishi ,  Takayuki Matsumoto ,  Masami Matsuda ,  Atsushi Yukita

IPC分类号： B01D1712

CPC分类号： G21F9/04

摘要： Radioactive laundry liquid wastes are supplied in a liquid waste heating vessel. Hydrogen peroxide and an alkali solution are supplied to the liquid waste heating vessel. The pH of the radioactive laundry liquid wastes is adjusted to 7 or higher by the alkali solution. The radioactive laundry liquid wastes are heated to 50° C. or higher by a heating device and introduced to first and second aeration vessels. The temperature is controlled by a device in accordance with the value measured by a thermometer. Ozone is supplied from an ozone generator by way of an ozone gas discharge port to the first aeration vessel. Ozone discharged from the first aeration vessel is introduced from the ozone gas discharge port to the second aeration vessel. Therefore, the amount of ozone dissolved into the radioactive laundry liquid wastes is increased so that the amount of hydroxy radicals formed for decomposing organic substances increases, since the laundry liquid wastes are heated to 50° C. or higher under the presence of hydrogen peroxide.

摘要翻译： 放射性洗衣液废液供应在液体废物加热容器中。 将过氧化氢和碱溶液供给至废液加热容器。 放射性洗衣液废物的pH值通过碱溶液调节至7以上。 放射性洗衣液废物通过加热装置加热至50℃以上，并被引入第一和第二通气容器。 根据由温度计测量的值由设备控制温度。 臭氧从臭氧发生器通过臭氧气体排放口供应到第一通气容器。 从第一曝气容器排出的臭氧从臭氧气体排放口引入第二曝气容器。 因此，由于在过氧化氢的存在下将洗衣液废弃物加热至50℃以上，所以溶解于放射性洗涤用液体废物中的臭氧的量增加，从而形成用于分解有机物质的羟基自由基的量增加。

公开(公告)号：US06502520B1

公开(公告)日：2003-01-07

申请号：US09600317

申请日：2000-07-13

申请人： Takashi Nishi ,  Hideo Hashida ,  Toshiaki Matsuo ,  Takeyuki Kondo ,  Masami Matsuda ,  Kiyotaka Ueda

发明人： Takashi Nishi ,  Hideo Hashida ,  Toshiaki Matsuo ,  Takeyuki Kondo ,  Masami Matsuda ,  Kiyotaka Ueda

IPC分类号： F23B500

CPC分类号： F23G5/24 ,  F23G5/085 ,  F23G5/16 ,  F23G2202/20 ,  F23G2204/204 ,  F23G2209/18 ,  G21F9/308 ,  G21F9/32

摘要： An incineration and melting furnace has a furnace main body that is filled with a conductive heat generation body (for example, graphite). Radioactive combustible materials in contact with the conductive heat generation body are burnt and the radiaoactive incombustible materials are melted. The resultant exhaust gases and the molten products flow downwardly in the conductive heat generation body filled region and flow out of a molten product discharging port. Noxious gases such as dioxins contained in the exhaust gases are thermally decomposed into a non-toxic state in a high temperature portion of the conductive heat generation region.

摘要翻译： 焚烧熔化炉具有填充有导电性发热体（例如石墨）的炉主体。 与导电发热体接触的放射性可燃材料被燃烧，并且辐射不燃材料熔化。 所产生的废气和熔融产物在导电发热体填充区域中向下流动，并从熔融产物排出口流出。 废气中含有的二恶英等有害气体在导电性发热区域的高温部分被热分解成无毒状态。

公开(公告)号：US4880595A

公开(公告)日：1989-11-14

申请号：US303055

申请日：1989-01-27

申请人： Masami Matsuda ,  Kiyomi Funabashi ,  Takashi Nishi ,  Itaru Komori ,  Tsutomu Baba ,  Hideo Yusa ,  Shunsuke Uchida ,  Tetsuro Adachi ,  Katsumi Ohsumi ,  Tomohiro Sato

发明人： Masami Matsuda ,  Kiyomi Funabashi ,  Takashi Nishi ,  Itaru Komori ,  Tsutomu Baba ,  Hideo Yusa ,  Shunsuke Uchida ,  Tetsuro Adachi ,  Katsumi Ohsumi ,  Tomohiro Sato

IPC分类号： G21F9/12 ,  G21C19/42 ,  C02F1/42

CPC分类号： G21F9/12

摘要： A process and an apparatus for cleaning nuclear reactor cooling water with cation exchange resin whose ion-exchanging groups have a bonding energy of not more than 300 KJ/mole are disclosed, whereby the radiation exposure of operators in an atomic power plant can be considerably reduced, and the waste ion exchange resin can be readily disposed.

摘要翻译： 公开了一种用离子交换基团具有不超过300KJ /摩尔的键合能量的阳离子交换树脂清洗核反应堆冷却水的方法和装置，由此原子能发电厂中的操作者的辐射暴露可以大大降低 ，废弃离子交换树脂可以容易地设置。