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公开(公告)号：US5550857A
公开(公告)日：1996-08-27
申请号：US485625
申请日：1995-06-07
申请人： Ray S. Richards
发明人： Ray S. Richards
CPC分类号： G21F9/305 , C03B5/005 , C03B5/027 , C03B5/033 , C03B5/1875 , C03B5/26 , Y02P40/52 , Y02P40/57 , Y10S422/903
摘要： A waste vitrification apparatus (10) having rotatable mixer impeller (16) functioning as a shaft electrode (60) and metallic vessel (14) functioning as a vessel electrode (62). A stream (12) of waste material and vitrifiable material are mixed and melted in the vessel (14) for vitrification. The waste vitrification method converts a feed stream (12) by mixing the feed stream into a glass melt (13) and melting glass batch of the feed stream (12) to form a foamy mass. The stream is dispersed by the impeller (16) to form a foam which is then densified in a settling zone (22), recovered through a spout (24) and solidified in storage containers. An adjuster adjusts the location of the mixing impeller (16) in the vessel (14) to change the depth of the settling zone (22). The impeller (16) is mounted on a drive shaft (18) having a recirculating coolant flow.
摘要翻译： 一种具有用作轴电极（60）的旋转混合器叶轮（16）和用作容器电极（62）的金属容器（14）的废玻璃化装置（10）。 将废物和玻璃化物质的料流（12）混合并熔化在容器（14）中用于玻璃化。 废玻璃化方法通过将进料流混合到玻璃熔体（13）中并将进料流（12）的熔融玻璃批料混合以形成泡沫体来转化进料流（12）。 流由叶轮（16）分散以形成泡沫，然后在沉降区（22）中致密化，通过喷口（24）回收并固化在储存容器中。 调节器调节容器（14）中的混合叶轮（16）的位置以改变沉降区（22）的深度。 叶轮（16）安装在具有循环冷却剂流的驱动轴（18）上。
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公开(公告)号：US5190623A
公开(公告)日：1993-03-02
申请号：US335661
申请日：1989-03-29
申请人： Yuko Sasaki , Takashi Honda , Saburo Shoji , Shiro Kobayashi , Yasumasa Furutani
发明人： Yuko Sasaki , Takashi Honda , Saburo Shoji , Shiro Kobayashi , Yasumasa Furutani
CPC分类号： G21C19/46 , Y02W30/883 , Y10S422/903
摘要： In a nuclear fuel reprocessing plant for processing a used nuclear fuel by a nitric acid solution, the present invention provides a nuclear fuel reprocessing plant characterized by including electrolytic reduction means for reducing the valence of oxidizing metal ions consisting of the nuclear fuel and dissolved in the nitric acid solution while they are kept under the ionic state. In a processing method of a nuclear fuel reprocessing plant for processing a used nuclear fuel by a nitric acid solution, the present invention provides also a corrosion-proofing method of a nuclear fuel reprocessing plant characterized in that electrolytic reduction is carried out so that the valence of oxidizing metal ions consisting of the nuclear fuel and dissolved in the nitric acid solution is reduced while the metal ions are kept under the ionic state and NOx gas is also generated. The invention is directed to provide a nuclear fuel reprocessing plant and its corrosion-proofing method which prevents corrosion of equipment without allowing the precipitation of corrosive metal ions in a nitric acid solution as the metals.
摘要翻译： PCT No.PCT / JP88 / 00694 Sec。 371日期：1989年3月29日 102（e）日期1989年3月29日PCT提交1988年7月13日PCT公布。 出版物WO89 / 0122400 日本1989年2月9日。在通过硝酸溶液处理使用的核燃料的核燃料后处理装置中，本发明提供了一种核燃料后处理装置，其特征在于包括用于降低氧化金属离子的价态的电解还原装置， 核燃料并在硝酸溶液中溶解，同时保持在离子状态。 在利用硝酸溶液处理使用的核燃料的核燃料后处理装置的处理方法中，本发明还提供了核燃料后处理装置的防腐蚀方法，其特征在于，进行电解还原， 氧化由核燃料组成的金属离子并溶解在硝酸溶液中的金属离子被还原，同时金属离子保持在离子状态并且还产生NOx气体。 本发明旨在提供一种核燃料后处理装置及其防腐蚀方法，其防止设备的腐蚀，而不允许将硝酸溶液中的腐蚀性金属离子沉淀为金属。
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公开(公告)号：US4851155A
公开(公告)日：1989-07-25
申请号：US151196
申请日：1988-02-01
申请人： Yutaka Kanagawa , Kanjiro Ishizaki , Mitsuzo Ozawa
发明人： Yutaka Kanagawa , Kanjiro Ishizaki , Mitsuzo Ozawa
CPC分类号： G21F9/008 , G21F9/307 , Y10S422/903
摘要： A solidification processing apparatus for radioactive waste materials comprises a tank for a solidifying agent for solidifying the radioactive waste materials, a waste material vessel connected to the tank for the radioactive waste materials, a pouring control unit for controlling pouring of the solidifying agent into the vessel, and a heating and curing chamber for heating the vessel by an indirect heating unit after pouring the solidifying agent onto the waste materials in the vessel to polymerize and set the solidifying agent, thereby solidifying the radioactive waste materials. With this arrangement, the solidifying agent superior in impregnation is poured into a vessel filled with radioactive waste materials, whose poured amount is controlled by the pouring control unit. After pouring the solidifying agent into the vessel, the vessel is heated indirectly by an indirect heating unit in order to avoid deflagration if the solidifying agent is combustible. The solidifying agent is polymerized and set in a relatively short time by promoting the polymerization reaction of the agent to solidify the radioactive waste materials with stability.
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公开(公告)号：US4834936A
公开(公告)日：1989-05-30
申请号：US91753
申请日：1987-09-01
申请人： Yasuo Hirose
发明人： Yasuo Hirose
IPC分类号： G21C19/46
CPC分类号： G21C19/46 , Y02W30/883 , Y10S422/903
摘要： A continuous dissolution apparatus for spent nuclear fuel in which a container (2) for holding a dissolution processing solution (1) is continuously supplied with nitric acid from a feed port (3), while the processing solution is continuously drawn out from an outlet (4). Baskets (71-74) in the container are packed with spent-fuel chops (6), which are continuously dissolved by the processing solution. The container is provided with a solution reserving section (4) for lowering the concentration of radioiodine contained in the dissolution processing solution, and a partition wall (10) is formed between the solution reserving section and a container body. The dissolution processing solution having overflowed from the upper edge of the partition wall flows into the solution reserving portion (14) through a perforated plate column (11). The solution reserving portion is furnished with a heating coil (12) for heating the dissolution processing solution and generating steam, and a gas blow pipe (13) for injecting an inert or nitrogen oxide gas into the solution. Thus, elementary iodine within the dissolution processing solution of the solution reserving section is expelled from the off-gas outlet (5) of the container together with the steam, and the radioiodine concentration in the dissolution processing solution of the solution reserving section can be lowered.
摘要翻译： 一种用于废核燃料的连续溶解装置，其中用于保持溶解处理溶液（1）的容器（2）从进料口（3）连续地供给硝酸，同时处理溶液从出口 4）。 容器中的篮子（71-74）装有废燃料剁（6），其被处理溶液连续溶解。 容器设有用于降低溶解处理溶液中所含的放射性碘浓度的溶液保留部分（4），并且在溶液储存部分和容器体之间形成分隔壁（10）。 从分隔壁的上边缘溢出的溶解处理溶液通过多孔板塔（11）流入溶液保留部分（14）。 溶液保留部分配备有用于加热溶解处理溶液并产生蒸汽的加热线圈（12），以及用于将惰性或氮氧化物气体注入溶液中的气体吹送管（13）。 因此，溶液保留部的溶解处理液中的元素碘与蒸汽一起从容器的废气出口（5）排出，并且可以降低溶液保留部分的溶解处理溶液中的放射性碘浓度 。
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15.发明授权
公开(公告)号：US4760585A
公开(公告)日：1988-07-26
申请号：US936814
申请日：1986-12-02
CPC分类号： G21F9/32 , Y10S159/12 , Y10S422/903
摘要： Radioactive wastes are treated in a furnace which has electrodes for electric heating. The furnace has at the lower end an outlet for slag material as well as a gas discharge line. Its well is a self-supporting tubular body which is arranged detachably in a metal furnace housing. At the upper end of the well is a line for feeding water. Thereby, carbon-containing waste, possibly also carbon of a carbon bed, is reacted to form water gas (CO+H.sub.2), which is burned after purification in an exhaust gas plant. The outlet of the metal housing has a movable grate.
摘要翻译： 放射性废物在具有电加热用电极的炉中进行处理。 炉子在下端具有炉渣材料的出口以及气体排放管线。 它是一个自支撑的管体，可拆卸地布置在金属炉壳体中。 在井的上端是供水的线。 因此，含碳废物（也可能是碳床的碳）被反应形成在废气装置中净化后燃烧的水气（CO + H 2）。 金属外壳的出口有一个可移动的格栅。
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公开(公告)号：US4592898A
公开(公告)日：1986-06-03
申请号：US474527
申请日：1983-03-11
申请人： Friedrich Kaufmann
发明人： Friedrich Kaufmann
CPC分类号： G21F9/305 , Y10S422/903
摘要： The invention is directed to an apparatus vitrifying radioactive fission ducts in liquid solution. The liquid solution is pumped in metered quantities from a feed container to a vitrifying oven. The offgas occurring during vitrification is scrubbed of entrained radioactive dust particles and the like by a scrubbing liquid in a scrubber. In order to obtain a simplified sequence of method steps for metering the liquid solution and for scrubbing the offgas, the radioactive fission product solution from the feed container itself is used as the scrubbing liquid. This fission product solution is taken from the feed container and conducted to the counterflow scrubber through which it is passed in a direction opposite to the flow of the offgas. The fission product solution used as a scrubbing liquid is returned to the feed container after passing through the counterflow scrubber.
摘要翻译： 本发明涉及一种在液体溶液中玻璃化放射性裂变产物的装置。 液体溶液以计量的量从进料容器泵送到玻璃化炉。 在玻璃化过程中发生的废气通过洗涤器中的洗涤液体被夹带的放射性尘埃颗粒等进行擦洗。 为了获得用于计量液体溶液和洗涤废气的方法步骤的简化顺序，来自进料容器本身的放射性裂变产物溶液用作洗涤液体。 该裂变产物溶液从进料容器中取出并传导到逆流洗涤器，通过该反流洗涤器，其沿与废气流相反的方向通过。 用作洗涤液的裂变产物溶液在通过逆流洗涤器后返回给料容器。
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公开(公告)号：US4050638A
公开(公告)日：1977-09-27
申请号：US570079
申请日：1975-04-21
申请人： Isao Ito , Yoichi Karita
发明人： Isao Ito , Yoichi Karita
CPC分类号： G21F7/061 , G21F9/02 , Y10S422/903
摘要： Maintenance apparatuses for and improvements in a radioactive matter containing waste gas treating installation, which is capable of completely carrying out waste gas cleaning by means of ceramic filter element is disclosed. The installation is provided with at least one of the following three apparatuses or devices, i.e.A ceramic filter element exchange apparatus which is capable of preventing radioactive contamination caused by scattering of radioactive dust at the time of inspecting or exchanging the filter element and preventing an operator from being subjected to radiation internal exposure as well as rapidly exchanging a spent filter element for a new one by remote control;A ceramic filter element treating apparatus which can pulverize the spent filter element by mechanical power instead of human power in a short time so as to considerably reduce the spent ceramic filter element in volume and change it into a form which can easily be solidified; andA device having a sealed joint structure which is capable of securing the filter element to a support plate in a reliable and sealed manner by remote control.
摘要翻译： 公开了能够通过陶瓷过滤元件完全进行废气净化的含有废气处理装置的放射性物质的维护装置和改进装置。 该装置设置有以下三个装置或装置中的至少一个，即
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公开(公告)号：US3976762A
公开(公告)日：1976-08-24
申请号：US485839
申请日：1974-07-05
申请人： Gunter A. Kohler , Gary M. Pestel
发明人： Gunter A. Kohler , Gary M. Pestel
CPC分类号： A61K51/0489 , A61K2123/00 , Y10S422/903
摘要： Chemical complexes, useful as radiopharmaceuticals, are formed by reacting technetium-99m with substituted or unsubstituted alkyl monophosphonic acids and certain ester derivatives thereof. The complexes are formed by reducing pertechnetate ion chemically or electrolytically in the presence of the phosphonic acid. By chemical modification of the phosphonic acid complexing agent, it is possible to "tailor" complexes for kidney, liver or bone imaging. The complexes are normally used in a physiologically acceptable aqueous medium.
摘要翻译： 可用作放射性药物的化合物是通过使锝-99m与取代或未取代的烷基单膦酸及其某些酯衍生物反应形成的。 通过在膦酸的存在下化学或电解还原高锝酸盐离子形成络合物。 通过膦酸络合剂的化学修饰，可以“定制”复合物用于肾，肝或骨成像。 络合物通常用于生理上可接受的水性介质中。
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公开(公告)号：US3971732A
公开(公告)日：1976-07-27
申请号：US530144
申请日：1974-12-05
申请人： Gerhard Meier
发明人： Gerhard Meier
CPC分类号： G21F9/34 , G21F9/008 , G21F9/167 , G21F9/307 , Y10S422/903
摘要： An apparatus for fixing radioactive or toxic waste has an extruder including a mixing mechanism for intermingling and advancing the waste and a carrier material introduced into the extruder. The extruder has a heating zone with which there communicates a vapor outlet device having an observation window. Within the vapor outlet device there is disposed an arrangement for cleaning the window and an arrangement for removing deposits from those locations of the vapor outlet device that are adjacent the mixing mechanism. The condenser is coupled to a distillate accumulator with the interposition of two alternatingly operating filters for removing particles from the condensate obtained from the condenser. To the outlet of the extruder there is coupled a loading device in which containers are successively filled with the material discharged by the extruder. The loading device includes an interrupter bowl which receives the material discharged by the extruder during an exchange of an empty container for a filled container below the extruder outlet.
摘要翻译： 用于固定放射性或有毒废物的装置具有挤出机，其包括用于混合和推进废物的混合机构和引入挤出机的载体材料。 挤出机具有加热区，在该加热区中连通有具有观察窗的蒸气出口装置。 在蒸气出口装置内设置有用于清洁窗口的装置和用于从邻近混合机构的蒸气出口装置的那些位置移除沉积物的装置。 冷凝器连接到馏出物储存器，其中插入两个交替操作的过滤器，用于从冷凝器获得的冷凝物中除去颗粒。 在挤出机的出口处连接有装载装置，其中容器依次填充有由挤出机排出的材料。 装载装置包括断续器碗，该灭板器在更换挤出机出口下方的填充容器的空容器之前接收由挤出机排出的材料。
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公开(公告)号：UST939005I4
公开(公告)日：1975-10-07
申请号：US45285774
申请日：1974-03-20
CPC分类号： B01D3/00 , G21F9/08 , Y10S422/903
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