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1.发明授权Method of separating and purifying spent solvent generated in nuclear fuel cycle 失效在核燃料循环中分离和净化产生溶剂的方法
公开(公告)号：US5110507A
公开(公告)日：1992-05-05
申请号：US673064
申请日：1991-03-22
申请人： Katsuyuki Ohtsuka , Isao Kondo , Takashi Okada
发明人： Katsuyuki Ohtsuka , Isao Kondo , Takashi Okada
CPC分类号： G21F9/08
摘要： A method of separating and purifying a spent solvent generated in a nuclear fuel cycle and containing a phosphate and a higher hydrocarbon. This method comprises treating the spent solvent at a temperature not greater than the freezing point of the higher hydrocarbon but not less than the freezing point of the phosphate to selectively freeze the higher hydrocarbon, and separating a resulting frozen solid mainly composed of the higher hydrocarbon from a remaining solution containing the phosphate in a higher concentration. The remaining solution may further be subjected to low-temperature vacuum distillation to separate the solution into the phosphate and a deterioration product thereof.
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公开(公告)号：US4981616A
公开(公告)日：1991-01-01
申请号：US400220
申请日：1989-08-29
申请人： Katsuyuki Ohtsuka , Isao Kondoh , Toru Suzuki
发明人： Katsuyuki Ohtsuka , Isao Kondoh , Toru Suzuki
CPC分类号： G21F9/08
摘要： In a method for recovering plutonium and uranium from spent nuclear fuel by solvent extraction having solvent consisting of tri-n-butyl phosphate, dibutyl phosphate and n-dodecane, the improvement comprises separating the n-dodecane from the phosphate by freeze-drying and separating the phosphate from each other and residual impurities by fractional distillation.
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公开(公告)号：US4364859A
公开(公告)日：1982-12-21
申请号：US168144
申请日：1980-07-14
IPC分类号： C01G43/025 , C01G56/00 , G21C3/00 , G21C3/62 , G21C21/00 , G21C21/02 , G21F9/16 , H05B6/80 , G21F9/08
CPC分类号： G21F9/16 , C01G43/025 , C01G56/005 , C01G56/007 , G21C3/623 , H05B6/80 , C01P2006/10 , H05B2206/045 , Y02E30/38
摘要： A method for the heat treatment of a radioactive substance by microwave power comprising preparing a nitrate solution of uranium, thorium, plutonium or a mixture thereof, and applying to the nitrate solution microwave energy sufficient to directly convert the nitrate solution into an oxide powder of uranium, thorium, plutonium or a mixture thereof, respectively. Such oxide powder is suitable for the manufacture of nuclear fuel pellets.
摘要翻译： 一种通过微波功率热处理放射性物质的方法，包括制备铀，钍，钚或其混合物的硝酸盐溶液，并向硝酸盐溶液施加足以将硝酸盐溶液直接转化成铀氧化物粉末的微波能量 ，钍，钚或其混合物。 这种氧化物粉末适用于制造核燃料颗粒。
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公开(公告)号：US4591454A
公开(公告)日：1986-05-27
申请号：US642750
申请日：1984-08-21
申请人： Katsuyuki Ohtsuka , Ryukichi Mizuno , Koji Yanagida , Kazuo Kitagawa , Atsuhiro Ochiai , Minoru Harada , Hiroshi Matsumoto
发明人： Katsuyuki Ohtsuka , Ryukichi Mizuno , Koji Yanagida , Kazuo Kitagawa , Atsuhiro Ochiai , Minoru Harada , Hiroshi Matsumoto
CPC分类号： C22B9/18 , B22D23/10 , C22B7/003 , H05B3/60 , Y02P10/212
摘要： An apparatus for melting and treating metal wastes including radioactive wastes, including a melting and treating vessel formed of the upper surface of a truck and split mold, wherein metal wastes are charged into the vessel in a closed system and melted by an electroslag melting method using a non-consumable electrode. This invention also provides a method which includes the steps of charging a slag melt starting agent and slag into the vessel in layers, and passing electricity through the non-consumable electrode to thereby heat the starting agent.
摘要翻译： 一种用于熔化和处理包括放射性废物在内的金属废物的设备，包括由卡车和分模的上表面形成的熔化和处理容器，其中金属废物在封闭系统中装入容器中并通过电渣熔化方法熔化，使用 非消耗性电极。 本发明还提供了一种方法，其包括以下步骤：将熔渣起始剂和炉渣以层间方式装入容器中，并使电通过非消耗性电极从而加热起始剂。
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公开(公告)号：US4400604A
公开(公告)日：1983-08-23
申请号：US239479
申请日：1981-03-02
申请人： Katsuyuki Ohtsuka , Hiroaki Miyo , Daisaku Hayashi
发明人： Katsuyuki Ohtsuka , Hiroaki Miyo , Daisaku Hayashi
CPC分类号： H05B6/78 , B01F9/0007 , B01F9/0041 , B01F9/06 , B01J19/126 , G21F9/14 , H05B6/784 , B01J2219/1215 , B01J2219/187 , H05B2206/045
摘要： A substance such as radioactive liquid waste is heat treated using microwave by introducing the substance into a vessel made of a material reflective to microwave and containing spherical bodies made mainly of a material transmissive (i.e. transparent) to microwave. Microwave is applied to the substance while imparting movement to the spherical bodies. The substance is heat treated while in contact with the spherical bodies and is separated from the spherical bodies and pulverized by the friction and collision between the moving spherical bodies. An apparatus for carrying out the method is described.
摘要翻译： 通过将物质引入到由微波反射的材料制成的容器中并且包含主要由透射（即，透明的）材料制成的球形体，微波对诸如放射性废液的物质进行热处理。 微波施加到物质同时赋予球体运动。 该物质在与球体接触的同时进行热处理，并与球体分离并通过移动的球体之间的摩擦和碰撞而粉碎。 描述了用于执行该方法的装置。
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公开(公告)号：US4980093A
公开(公告)日：1990-12-25
申请号：US362913
申请日：1989-06-08
申请人： Katsuyuki Ohtsuka , Isao Kondoh , Takeshi Kawasaki
发明人： Katsuyuki Ohtsuka , Isao Kondoh , Takeshi Kawasaki
CPC分类号： G21F9/08
摘要： A high-level radioactive waste liquid, produced in a reprocessing plant, is treated by a freeze-drying step. A low-level radioactive waste liquid containing water, nitric acid and nuclides is obtained from the sublimate of the freeze-drying step. Fission products, actinides, corrosion products (iron, chromium, nickel, etc.), sodium nitrate and sodium hydroxide, not sublimated, are separated as a residue. An alkaline solution such as sodium hydroxide solution is added to the residue to dissolve sodium nitrate and sodium hydroxide. The dissolved nitrate and hydroxide are then separated from the residue containing fission products and the corrosion products.
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公开(公告)号：US4895678A
公开(公告)日：1990-01-23
申请号：US363305
申请日：1989-06-08
申请人： Katsuyuki Ohtsuka , Jin Ohuchi , Hideaki Tamai
发明人： Katsuyuki Ohtsuka , Jin Ohuchi , Hideaki Tamai
CPC分类号： G21F9/30 , G21F9/14 , G21F9/308 , Y10S159/12
摘要： A method for thermal decomposition treatment of a radioactive waste uses an apparatus comprising a container for holding molten matter of a radioactive waste containing a sodium compound, a pair of electrodes contacting the molten matter, and a power source for applying voltage between the electrodes while changing the polarity thereof every several tens of seconds. In this apparatus, the molten matter can be heated in the container by Joule heat, which is evolved by electric current directly flowed through the molten matter, so that the sodium compound contained in the radioactive waste can be decomposed, vaporized and removed to recover a stabilized radioactive solid as a residue in the container.
摘要翻译： 放射性废物的热分解处理方法使用的装置包括容纳含有钠化合物的放射性废物的熔融物质的容器，与熔融物接触的一对电极以及在电极之间施加电压的电源，同时改变 其极性每隔几十秒。 在该装置中，可以通过焦耳热在容器中加热熔融物质，焦耳热通过直接流过熔融物质的电流放出，使得放射性废物中所含的钠化合物能够分解，蒸发并除去 稳定的放射性固体作为容器中的残留物。
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公开(公告)号：US4587098A
公开(公告)日：1986-05-06
申请号：US264406
申请日：1981-05-18
申请人： Katsuyuki Ohtsuka , Ryukichi Mizuno , Hitoshi Miyazaki , Toshio Fukuzuka , Kazutoshi Shimogori , Hiroshi Satoh , Fumio Kami Kubo
发明人： Katsuyuki Ohtsuka , Ryukichi Mizuno , Hitoshi Miyazaki , Toshio Fukuzuka , Kazutoshi Shimogori , Hiroshi Satoh , Fumio Kami Kubo
IPC分类号： B09B3/00 , B01J19/02 , B29B11/00 , B29B17/00 , C23F11/04 , G21F9/00 , G21F9/30 , G21F9/32 , C23F11/18
CPC分类号： G21F9/32 , B01J19/02 , C23F11/04 , G21F9/30 , B01J2219/0277 , Y10S241/38
摘要： A method of minimizing corrosion deterioration and hydrogen absorption embrittlement of tantalum encountered in performing acid digestion of organic waste matter put in an acid digestion kettle of tantalum containing high temperature high concentration sulfuric acid includes the addition of nitric acid, nitrous acid, nitrates, nitrites and/or nitrogen oxides to the sulfuric acid bath.
摘要翻译： 将在含有高温高浓度硫酸的钽的酸消化釜中进行酸性消化的有机废弃物的酸消化中遇到的钽的腐蚀劣化和氢吸收脆化最小化的方法包括加入硝酸，亚硝酸，硝酸盐，亚硝酸盐和 /或氮氧化物加入到硫酸浴中。
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9.发明授权Method of recovering and storing radioactive iodine by freeze vacuum drying process 失效通过冷冻真空干燥过程回收和储存放射性碘的方法
公开(公告)号：US5252258A
公开(公告)日：1993-10-12
申请号：US746818
申请日：1991-08-15
申请人： Katsuyuki Ohtsuka , Jin Ohuchi , Toru Suzuki
发明人： Katsuyuki Ohtsuka , Jin Ohuchi , Toru Suzuki
CPC分类号： C22B7/02 , B01D53/68 , G21C19/42 , Y02P10/212
摘要： The invention provides a method of recovering and storing radioactive iodine by a freeze vacuum drying process, in which off-gas generated when spent fuel is subjected to shearing and dissolving treatments is scrubbed and, when necessary, is subjected to a precipitation treatment by addition of additives, after which waste liquid containing radioactive iodine is freeze-dried by a freeze vacuum drying process to recover radioactive iodine as iodine compounds. As a result, since the radioactive iodine does not vaporize, release of the radioactive iodine into the environment can be eliminated. In addition, consumption of a collecting agent such as silver zeolite for collecting vaporized radioactive iodine can be reduced. The iodine compounds containing the recovered radioactive iodine is given the same composition as a stable, naturally occurring mineral and is solidified and mineralized as by a high-pressure press. This makes it possible to store long half-life .sup.129 I radioactive iodine safely for an extended period by sealing recovered radioactive iodine in stable minerals for a long period of time.
摘要翻译： 本发明提供一种通过冷冻真空干燥方法回收和储存放射性碘的方法，其中废燃料经受剪切和溶解处理时产生的废气被擦洗，并且在必要时通过加入沉淀处理进行沉淀处理 添加剂，然后通过冷冻真空干燥法将含有放射性碘的废液冷冻干燥，以回收作为碘化合物的放射性碘。 结果，由于放射性碘不蒸发，因此可以消除放射性碘向环境的释放。 此外，可以减少用于收集蒸发的放射性碘的收集剂如银沸石的消耗。 含有回收的放射性碘的碘化合物具有与稳定的天然存在的矿物相同的组成，并通过高压压机固化和矿化。 这可以通过长时间密封稳定矿物中的回收放射性碘，长时间保存长半衰期的129I放射性碘。
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公开(公告)号：US4844838A
公开(公告)日：1989-07-04
申请号：US154213
申请日：1988-02-10
IPC分类号： G21F9/06
CPC分类号： G21F9/06
摘要： A method of treatment of a radioactive liquid waste containing fission products and a thermally decomposable sodium compound which comprises heating the liquid waste to convert the sodium compound into oxides of sodium, converting the oxides into sodium, hydroxide, reacting the sodium hydroxide with an alcohol to form a sodium alcoholate, separating the sodium alcoholate from an impurity residue essentially comprising fission products, decomposing the separated sodium alcoholate to form sodium hydroxide and recovering the sodium hydroxide.
摘要翻译： 一种处理包含裂变产物和可热分解钠化合物的放射性废液的方法，包括加热液体废物以将钠化合物转化成钠的氧化物，将氧化物转化为钠，氢氧化物，使氢氧化钠与醇反应 形成醇钠，将醇钠与基本上包含裂变产物的杂质残留物分离，将分离的醇钠分解形成氢氧化钠并回收氢氧化钠。
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