公开(公告)号：US6004377A

公开(公告)日：1999-12-21

申请号：US97707

申请日：1998-06-16

申请人： Shin Tamata ,  Toru Tsubaki ,  Akio Nadamura ,  Koji Ito ,  Toshio Ohi ,  Hiromoto Ohno

发明人： Shin Tamata ,  Toru Tsubaki ,  Akio Nadamura ,  Koji Ito ,  Toshio Ohi ,  Hiromoto Ohno

IPC分类号： F17D1/02 ,  B01D53/40 ,  B01D53/68 ,  C01B17/45 ,  F25J3/06 ,  H01H33/56 ,  H02B13/055 ,  B01D53/04 ,  B01D15/08

CPC分类号： C01B17/453 ,  B01D53/685 ,  H01H33/56 ,  H02B13/055 ,  Y02C20/30 ,  Y02P20/151

摘要： SF.sub.6 gas is collected from the inside of a gas insulated machine during maintenance and inspection and is refined. Compositions of the refined SF.sub.6 gas are analyzed and confirmed to be reusable at the site. In the process of SF.sub.6 gas collecting and refining, acidic gases are neutralized and removed by a dry method using filters and the refined SF.sub.6 gas is collected in a collecting tank. In particular, after the refining, the composition of the collected SF.sub.6 gas is measured and confirmed by analysis equipment to quantitatively confirm whether or not the refined SF.sub.6 gas is reusable.

摘要翻译： SF6气体在维护和检查期间从气体绝缘机器的内部收集并精制。 分析并确认精炼SF6气体的组成在现场可重复使用。 在SF6气体收集和精炼过程中，通过使用过滤器的干法将酸性气体中和并除去，精炼的SF6气体被收集在收集罐中。 特别是精炼后，通过分析装置测定收集的SF 6气体的组成，并确认精炼的SF6气体是否可再利用。

公开(公告)号：US5977427A

公开(公告)日：1999-11-02

申请号：US658646

申请日：1996-06-05

申请人： Shin Tamata ,  Satoru Ohashi ,  Toshihide Takano ,  Hisao Yokoyama ,  Toshihiro Mori

发明人： Shin Tamata ,  Satoru Ohashi ,  Toshihide Takano ,  Hisao Yokoyama ,  Toshihiro Mori

IPC分类号： B01D53/14 ,  A62D101/22 ,  B01D53/86 ,  B01D53/70

CPC分类号： A62D3/38 ,  A62D3/20 ,  A62D3/35 ,  A62D3/37 ,  B01D53/8662 ,  A62D2101/22 ,  A62D2203/04 ,  A62D2203/10 ,  Y02C20/30

摘要： A process is provided for the destruction of organohalogen compounds, such as methyl chloride, chloroform, carbon tetrachloride, etc., by mixing the organohalogen compounds with a heated carrier gas, such as nitrogen, argon or air, and either steam or water to form a mixture; supplying the mixture to a catalyst, such as titanium oxide/tungsten oxide, to decompose the organohalogen compounds into halogens and hydrogen halides, such as chlorine, hydrochloric acid, fluorine and hydrofluoric acid; conducting the halogen and hydrogen halide contaminated gas through a bent path, created by a baffle that prevents the entry of mist or droplets into the catalyst chamber, into a cooling section where the halogen and hydrogen halide contaminated gas is sprayed with water to cool the gas to a temperature low enough to prevent the formation of dioxines. An alkaline agent, such as sodium hydroxide, can be added to the cooling water to neutralize the halides and hydrogen halides.

摘要翻译： 通过将有机卤素化合物与加热的载气如氮气，氩气或空气以及蒸汽或水混合形成有机卤素化合物如氯甲烷，氯仿，四氯化碳等的方法，形成 混合物; 将混合物供给到氧化钛/氧化钨等催化剂中，将有机卤素化合物分解为卤素，卤化氢，如氯，盐酸，氟，氢氟酸; 通过弯曲路径导通卤素和卤化氢污染气体，该弯曲路径由防止雾或液滴进入催化剂室的挡板形成冷却段，在该冷却段中卤素和卤化氢污染的气体用水喷洒以冷却气体 达到足够低的温度以防止形成二恶英。 可以向冷却水中加入碱性试剂如氢氧化钠以中和卤化物和卤化氢。

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：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

IPC分类号： G21F9/06 ,  B01D61/36 ,  C02F1/44 ,  G21F9/08 ,  G21F9/12

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

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：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：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。

公开(公告)号：US4755332A

公开(公告)日：1988-07-05

申请号：US850667

申请日：1986-04-11

申请人： Hiroko Mizuno ,  Makoto Kikuchi ,  Shin Tamata ,  Satoru Ohashi ,  Tadashi Sakuraoka

发明人： Hiroko Mizuno ,  Makoto Kikuchi ,  Shin Tamata ,  Satoru Ohashi ,  Tadashi Sakuraoka

IPC分类号： G21F9/30 ,  B30B11/02 ,  B30B15/00 ,  G21F9/00 ,  G21F9/34 ,  G21C21/00 ,  G21F9/36

CPC分类号： G21F9/34 ,  B30B11/025 ,  B30B15/0017 ,  Y10S100/903 ,  Y10S100/906 ,  Y10S425/812

摘要： A method of and apparatus for pelletizing a radioactive waste powder is disclosed. The apparatus includes a pelletizing section, and a pelletizing die which has one end facing a powder receiving cavity formed in the pelletizing section and the other end exposed to the atmosphere, and a through bore is so formed in the die as to pass from the one end to the other end. A first pelletizing rod can be inserted into and pulled out of the through bore from the one end of the die through the cavity, and a second pelletizing rod can be inserted into a pulled out of the through bore from the other end of the die. The first and second rods are arranged such that, when the second rod takes a predetermined position in the through bore, the first rod is inserted through the receiving cavity into the through bore, thereby enabling the pelletizing operation of the powder within the through bore. The structure is adopted for allowing air compressed in the through bore to be discharged into the cavity without causing the compressed air to leak into the atmosphere during the pelletizing operation.

摘要翻译： 公开了一种用于造粒放射性废粉的方法和装置。 该设备包括造粒部分和造粒模具，其一端朝向形成在造粒部分中的粉末容纳腔，而另一端暴露于大气，并且通孔如此形成在模具中以从一个 结束对方 第一颗粒棒可以从模具的一端插入并从通孔中拉出，并且第二颗粒棒可以从模具的另一端插入从通孔中拉出。 第一杆和第二杆被布置成使得当第二杆在通孔中采取预定位置时，第一杆通过接收腔插入通孔中，从而使得粉末在通孔内的造粒操作。 采用该结构，使得在通气孔中压缩的空气能够在造粒操作期间将压缩空气泄漏到大气中。

公开(公告)号：US4671897A

公开(公告)日：1987-06-09

申请号：US697384

申请日：1985-02-01

申请人： Kazuhide Mori ,  Shin Tamata ,  Makoto Kikuchi

发明人： Kazuhide Mori ,  Shin Tamata ,  Makoto Kikuchi

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

CPC分类号： G21F9/06 ,  G21F9/302

摘要： Radioactive waste is first converted into hardly water-soluble powder (including a water-insoluble powder) and then solidified with a hydraulic solidifier in a solidification vessel. The radioactive waste may be powdered (including granulated and encapsulated) by incorporating the radioactive waste with a substance which is capable of reacting with the water-soluble salt contained in the radioactive waste to form a hardly water-soluble salt (including a water-insoluble salt) and then powdering the mixture with drying, or by powdering the radioactive waste with drying, granulating the powder with drying and then microencapsulating the granules with a hardly water-soluble substance (including water-insoluble substance). The hardly water-soluble salts are preferably calcium salts, and the additives are preferably calcium hydroxide solution or solvent of combination of dichloromethane solution and hexane.

摘要翻译： 首先将放射性废物转化为几乎不溶于水的粉末（包括水不溶性粉末），然后用固化容器中的液压固化器固化。 放射性废物可以通过将放射性废物与能够与放射性废物中所含的水溶性盐反应形成几乎不溶于水的盐的物质（包括不溶于水的盐） 盐），然后干燥粉碎混合物，或通过干燥粉碎放射性废物，干燥制粒粉碎，然后用几乎不溶于水的物质（包括水不溶性物质）将颗粒微胶囊化。 难溶的水溶性盐优选为钙盐，添加剂优选氢氧化钙溶液或二氯甲烷溶液与己烷组合的溶剂。

公开(公告)号：US4632779A

公开(公告)日：1986-12-30

申请号：US613195

申请日：1984-05-23

申请人： Hiroko Mizuno ,  Makoto Kikuchi ,  Susumu Horiuchi ,  Shin Tamata

发明人： Hiroko Mizuno ,  Makoto Kikuchi ,  Susumu Horiuchi ,  Shin Tamata

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

CPC分类号： G21F9/008 ,  G21F9/302 ,  G21F9/34

摘要： The invention is concerned with radioactive waste pellets in solidified form in which radioactive waste pellets including light waste pellets having specific gravities smaller than that of a filler are solidified with the filler in a container. A cover disposed in an opening portion of the container is provided with filler injection ports which do not permit the passage of the light waste pellets. The invention is further related to a process for forming radioactive waste pellets in solidified form by injecting the filler through the filler injection ports formed in the cover, so that the radioactive waste pellets and the filler are uniformly solidified.

摘要翻译： 本发明涉及固化形式的放射性废料颗粒，其中包含比填料小的比重的轻废料颗粒的放射性废料颗粒用填料固化在容器中。 设置在容器的开口部分中的盖设置有不允许轻废料丸粒通过的填充剂注入口。 本发明还涉及通过将形成在盖中的填料注入口注入填料而形成固化形式的放射性废料颗粒的方法，使得放射性废料颗粒和填料均匀地固化。