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1.发明授权Method for solidification of waste, and apparatus, waste form, and solidifying material therefor 失效废弃物固化方法，装置，废物形式及固化材料
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
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。
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公开(公告)号：US4775495A
公开(公告)日：1988-10-04
申请号：US826677
申请日：1986-02-06
申请人： Tatsuo Izumida , Tsutomu Baba , Akihiko Noie , Masaru Sonobe , Makoto Kikuchi
发明人： Tatsuo Izumida , Tsutomu Baba , Akihiko Noie , Masaru Sonobe , Makoto Kikuchi
CPC分类号： G21F9/162
摘要： The process of the present invention comprises adding an alkaline earth metal hydroxide such as barium hydroxide to a radioactive liquid waste containing sodium sulfate as the main component to convert the latter into an insoluble alkaline earth metal salt such as barium sulfate, adding silicic acid to by-product sodium hydroxide to prepare water glass and solidifying the radioactive insoluble alkaline earth metal salt with the water glass. According to this process, exudation of radioactive substances from the solid can be prevented and the solid having a high durability can be obtained at a low cost.
摘要翻译： 本发明的方法包括将碱土金属氢氧化物如氢氧化钡加入到以硫酸钠为主要成分的放射性废液中，将其转化为不溶性碱土金属盐如硫酸钡，将硅酸加入到 - 产品氢氧化钠，制备水玻璃，并用水玻璃固化放射性不溶性碱土金属盐。 根据该方法，能够防止放射性物质从固体渗出，能够以低成本获得耐久性高的固体。
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3.发明授权
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
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。
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公开(公告)号：US4793947A
公开(公告)日：1988-12-27
申请号：US852821
申请日：1986-04-16
申请人： Tatsuo Izumida , Hideo Yusa , Kiyomi Funabashi , Makoto Kikuchi , Shin Tamata
发明人： Tatsuo Izumida , Hideo Yusa , Kiyomi Funabashi , Makoto Kikuchi , Shin Tamata
CPC分类号： G21F9/162
摘要： The present invention relates to a method and an apparatus for producing a waste package of radioactive waste containing particles of radioactive waste material of low modulus of elasticity, particles of radioactive waste material of high modulus of elasticity, and a solidifying agent in which the particles of radioactive waste material of low modulus of elasticity and the particles of radioactive waste material of high modulus of elasticity are fixed in an almost uniformly dispersed state. According to this invention, the radioactive waste generated from nuclear power plants can be greatly reduced in volume and also a waste package of radioactive waste with high strength and excellent water resistance can be obtained.
摘要翻译： 本发明涉及一种生产含有低弹性模量的放射性废料颗粒，高弹性模量的放射性废料颗粒和固化剂的放射性废物废物包装方法和装置， 低弹性模量的放射性废料和高弹性模量的放射性废料颗粒以几乎均匀分散的状态固定。 根据本发明，可以大大减少核电站产生的放射性废物的体积，并且还可以获得具有高强度和优异的耐水性的放射性废物的废物包装。
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5.发明授权
公开(公告)号：US4481089A
公开(公告)日：1984-11-06
申请号：US582543
申请日：1984-02-22
申请人： Tatsuo Izumida , Koji Kato , Fumio Kawamura
发明人： Tatsuo Izumida , Koji Kato , Fumio Kawamura
摘要： The present invention provides a method for decontaminating metal components which have been contaminated on their surfaces with radioactive substances, characterized in that radioactivated oxide films on the metal surfaces are electrolytically removed by an alternating electrolysis method in a neutral salt solution. According to the invention, oxides and hydroxides for metals removed by the electrolytic treatment are separated from the electrolyte and solidified. The method of this invention makes it possible to positively remove the radioactivated oxide films from a base metal.
摘要翻译： 本发明提供了一种用放射性物质污染其表面的金属成分去污的方法，其特征在于，在中性盐溶液中通过交替电解法将金属表面上的放射性活化氧化物膜电解除去。 根据本发明，通过电解处理除去的金属的氧化物和氢氧化物与电解质分离并固化。 本发明的方法使得可以从母体金属中肯定地去除放射活性氧化物膜。
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公开(公告)号：US5732362A
公开(公告)日：1998-03-24
申请号：US358955
申请日：1994-12-19
摘要： The present invention relates to a method for treating radioactive laundry waste water generated from a nuclear power plant, nuclear fuel reprocessing plant, or radioactive nuclides handling facilities, and provides a method for treating the waste water safely and for reducing the volume of generated radioactive waste to a minimum. Radioactive laundry waste water containing a detergent of which major contents are a nonionic surface active agent and inorganic builders is concentrated by an evaporating concentrator, the concentrated waste water is dried and pulverized to dry powder by a rotary centrifugal thin film dryer, and the dry powder is incinerated. By using the above detergent, foaming at the concentration can be reduced, and the concentrated waste water can be easily dried and pulverized. Further, the dried powder can be incinerated stably and safely without influencing undesirable effect on the body of the incinerator. In accordance with the present invention, laundry waste water can be treated simply and safely, and the final volume of radioactive waste can be reduced to minimum.
摘要翻译： 本发明涉及一种用于处理核电厂，核燃料后处理厂或放射性核素处理设备产生的放射性洗衣废水的方法，并提供了一种安全处理废水并减少产生的放射性废物体积的方法 至少。 含有主要成分为非离子表面活性剂的洗涤剂和无机助洗剂的放射性洗涤废水通过蒸发浓缩器浓缩，浓缩废水通过旋转式离心薄膜干燥机干燥并粉碎成干燥粉末， 被焚烧 通过使用上述洗涤剂，可以降低浓度的发泡，并且可以容易地将浓缩的废水干燥和粉碎。 此外，干燥粉末可以稳定和安全地焚烧，而不会影响对焚烧炉体的不良影响。 根据本发明，可以简单和安全地处理洗衣废水，并将放射性废物的最终体积降低到最小。
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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
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。
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