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1. 发明授权

US5489737A Radioactive waste processing system 失效
标题翻译：放射性废物处理系统
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。

2. 发明授权

US5256338A Solidifying materials for radioactive waste disposal, structures made of said materials for radioactive waste disposal and process for solidifying of radioactive wastes 失效
标题翻译：用于放射性废物处理的固化材料，用于放射性废物处理的所述材料结构和放射性废物固化过程
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

3. 发明授权

US5202062A Disposal method of radioactive wastes 失效
标题翻译：放射性废物处置方法
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。

4. 发明授权

US4931222A Process for treating radioactive liquid waste containing sodium borate and solidified radioactive waste 失效
标题翻译：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
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。

5. 发明授权

US5114622A Method of cementing radioactive waste and cemented body 失效
标题翻译：放射性废物和固化体的方法
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.

6. 发明授权

US4804498A Process for treating radioactive waste liquid 失效
标题翻译：处理放射性废液的方法
公开(公告)号：US4804498A
公开(公告)日：1989-02-14
申请号：US938798
申请日：1986-12-08
申请人： Hiroko Mizuno , Makoto Kikuchi , Shin Tamata , Tatsuo Izumida , Tsutomu Baba
发明人： Hiroko Mizuno , Makoto Kikuchi , Shin Tamata , Tatsuo Izumida , Tsutomu Baba
IPC分类号： G21F9/00 , G21F9/10 , G21F9/12 , G21F9/14 , G21F9/16 , G21F9/30 , G21F9/08
CPC分类号： G21F9/10 , G21F9/12 , G21F9/14 , G21F9/302
摘要： A soluble salt (sodium sulfate or sodium borate (Na.sub.2 SO.sub.4 or Na.sub.2 B.sub.4 O.sub.7) contained as the main component in a concentrated radioactive waste liquid generated in the BWR power plant or the PWR power plant is insolubilized and precipitated, sodium hydroxide (NaOH formed in the insolubilization is separated from the precipitate and the radioactive waste liquid slurry containing the precipitate is solidified with a hydraulic solidifying material. Since the separated caustic soda (NaOH) is free of radioactive substances, it can be easily utilized again, and since the radioactive substances are stably fixed in the solidified body, leakage of radioactivity from the solidified body can be greatly reduced.
摘要翻译：在BWR发电厂或PWR发电厂中生成的浓缩放射性废液中作为主要成分的可溶性盐（硫酸钠或硼酸钠（Na2SO4或Na2B4O7））不溶解和沉淀，氢氧化钠（不溶解形成的NaOH为与沉淀物分离，含有沉淀物的放射性废液浆料用液压固化材料固化，由于分离的苛性钠（NaOH）不含放射性物质，因此可以方便地再利用，由于放射性物质稳定在凝固体中，可以大大降低来自凝固体的放射性泄漏。

7. 发明授权

US5045241A Method for solidifying radioactive wastes 失效
标题翻译：固化放射性废物的方法
公开(公告)号：US5045241A
公开(公告)日：1991-09-03
申请号：US330083
申请日：1989-03-09
申请人： Osamu Kuriyama , Kiyomi Funabashi , Tsutomu Baba , Masami Matsuda , Koichi Chino , Makoto Kikushi
发明人： Osamu Kuriyama , Kiyomi Funabashi , Tsutomu Baba , Masami Matsuda , Koichi Chino , Makoto Kikushi
IPC分类号： G21F9/36 , G21F9/00 , G21F9/30 , G21F9/34
CPC分类号： G21F9/302 , G21F9/008 , G21F9/34
摘要： A method of solidifying radioactive wastes comprising the steps of substituting the atmosphere inside a container packed with radioactive waste with a condensable vapor, pouring a matrix material into said container and thereafter condensing said vapor. The condensable vapor can be steam and the matrix material can be alkaline organic material.
摘要翻译： PCT No.PCT / JP88 / 00596 Sec。 371日期：1989年3月9日 102（e）1989年3月9日PCT PCT 1987年7月10日PCT公布。公开号WO89 / 00753 日本1989年1月26日。一种固化放射性废物的方法，其特征在于，包括以可冷凝蒸气置换放射性废物的容器内的气氛，将基质材料倒入所述容器中，然后冷凝所述蒸气的步骤。可冷凝蒸汽可以是蒸汽，基质材料可以是碱性有机材料。

8. 发明授权

US5028298A Waste water concentrator and waste water disposal plant 失效
标题翻译：废水集中器和废水处理厂
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。

9. 发明授权

US5481061A Method for solidifying radioactive waste 失效
标题翻译：固化放射性废物的方法
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。

10. 发明授权

US4880595A Process and apparatus for cleaning nuclear reactor cooling water 失效
标题翻译：清洁核反应堆冷却水的工艺和设备
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。

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