• 专利附录
  • 专利说明
  • 权利要求
  • 类似技术
  • 同族专利
  • 引用文献
  • 法律状态
  • 优先权
    • 专利摘要:
    The invention relates to the processing of radioactive waste into ceramics and dp ceramization of low and high level nuclear waste can be used. The purpose of the invention is to simplify the method and increase its efficiency, achieved by using simple technology and inexpensive, readily available raw materials. The radioactive waste from the solution is bound in a synthetic orop. the ionic ion exchanger, mixed with a ceramizing agent at a ratio of 11-25%, water is added to a content of 23-27 wt.h. and fired to obtain shingles. In order to improve the binding of cesium, vermiculite is introduced into the mixture of components in an amount of 2 g wt.%. Simplification of the method is achieved by the fact that annealing is carried out at normal pressure and low temperature of ceramization of the mixture, and using red clay, kaolin, feldspar, monmorillonite, illite, quartz as a ceramic material allows to obtain a cheap end product. 1 hp f-ly.
    公开号:SU1279541A3
    申请号:SU3681798
    申请日:1983-12-27
    公开日:1986-12-23
    发明作者:Лехто Юкка；Миеттинен Йорма；Хейнонен Олли
    申请人:Иматран Войма Ой (Фирма)；
    IPC主号:
    专利说明:


    o The invention relates to a process for rotating the radioactive waste into ceramics. The purpose of the invention is to simplify the method, increase its efficiency by using simple and inexpensive technology, easy access to basic materials, for example, conventional ceramic raw materials, as well as improved radioactive waste binding to a ceramic material. The essence of the method is that the radioactive waste or sludge is bound in an inorganic ion exchanger, the inorganic ion exchange with the waste is mixed with the ceramic substance, the waste mixed with the ceramic substance is added to the content of 23-27 wt.% And about burn to obtain final product.
    The ceramics method of inorganic ion exchangers is based on inexpensive and readily available starting materials on conventional source materials of ceramic industry and on a simple technology suitable for t-1 and high-level waste. The raw materials for bricks and tiles are cheap and readily available. The shingles technology is simple and the firing temperature is scrub-comparative, and thus the evaporation of radioactive substances is prevented during the process. Synthetic and natural additives, such as vermt-culite or apatite, can be added to the tiles - which increase the stability of some substances in the tile. When firing the tiles, sallic pressing devices are not required and this significantly reduces the i-function: simplifies the method. Clay tiles, containing: no titanate, are glazed during firing and become slightly soluble. They can be covered with a passive surface sgmoem. As a result, there will be: in the metal container for tiles with medium and waste. The proposed method gives significant savings in volume, the maximum decrease in volume of the same size as for the core products „compared to bitumen and concrete products„
    After mixing with tile
    With clay, the mixture is stirred gently to make it obliqueable. Then it is molded into tiles. The shingles can be pressed to reduce porosity and dry three room
    temperature After that, it is dried at 150 ° C for at least 4 hours and cooled.
    The firing of the scion is carried out with;
    Bake
    heated with (s speed at iOOc / h. up to 1020-1060 С and extinctly
    darsing at a maximum temperature of 4-10 hours. After firing, the tile is cooled in a furnace
    The most important factor in tile quality in light of final storage is the solubility of waste isotopes from it. Sr, Cs and Co leaching rates from sodium titamate or
    ZrOj / KpacHaa clay (in the form of tiles) with evaporator waste concentrate is 10 -10 g / cm. D. Solubility of the sodium tinanate. Red clay with highly active
    waste-iH is an order of magnitude higher; Adding a vacuum of (1%) to a tile causes a decrease in solubility. Thus, the leaching rates correspond to the best borosilicate glass - ..
    The solubility characteristics of a tile can be improved by surface glazing or by sintering a non-active layer on the surface of the skull1 1 12 According to the proposed method, radioactive waste in a solution is bound in an inorganic ion exchanger such as titanate, zhubat, dirconate, or zirconium dioxide. To better bind some radioisotopes such as Cs, synthetic or n / 1-additive additives such as vermiculite, lumonite or apatite are introduced into the skids. In the case of diclating, the ion exchange should not be dried and crushed, and the tiled clay is added to the ion exchanger mixture from waste # 1 after saturation, so that the water content in the mixture is 23-27%. The weight of the ion-exchanger 1 to the tiled clay is P-25%. Materials5 used as ceramics include red clay kaolm ,, monmorillonite, feldspar illite and quartz from tile clay. Adding titanate to tile clays causes glazing of tiles, and tiles titanate / red clay have less porosity than tiles made of red clay only. The tile is ideal when its solubility allows its storage without any special shells. The tile has a very high mechanical strength, which is important for transportation and converse with it (bending strength of about 2030 MN / m. When the amount of ion exchange in the tile is no more than 15%, the evaporation of metals from the tile is minimal. 2.% at calcination temperature 020 ° C, Evaporation increases when increasing the quantification of the ion exchanger or the temperature.The optimum values for minimum evaporation of a 15% ion-mixing tile, a firing temperature of 1020 ° C and a firing time of 4 hours. More important wastes, such as evaporation waste concentrates, waste of isotopes from spent resin in reactors, high-level fuel processing waste, of the invention 1, A method for ceramization of radioactive waste, which consists of waste from a solution of radioactive waste. in an inorganic ion exchanger, which is then mixed with a ceramizing material and annealed to obtain the final product, characterized in that, in order to control and increase the efficiency of the process, as a ceramizing material using material from p da4 red clay, kaolin, montmorillonite, feldspar, illite, and quartz, or a mixture thereof, and as inorganic salts shcheskogo ionosbmennika - neorgazzdcheskie synthetic ion exchangers iz: a number; tntanate, niobate, zirconate, zirconia or mixtures thereof, when mixing a waste exchanger with a ceramic material, water is added to keep it in a mixture of 23-27% by weight, while the ratio of the ion exchanger with waste material to the ceramic material is 11 -25%, annealing is carried out at normal pressure and at the ceramization temperature of a mixture of synthetic inorganic ion exchangers with waste and ceramizing material. 2. Method POP.1, distinguished by the fact that, in order to improve the binding of radioactive waste in a ceramic material, when mixing the components, vermiculite is additionally introduced in an amount of 2 wt.%.
    权利要求:
    Claims (2)
    [1]
    1, The method of ceramicization of radioactive waste, consisting in the fact that
    1279541 4 waste from a solution of radioactive waste is bound in an inorganic ion exchanger, which is then mixed with a ceramic material and annealed 5 to obtain the final product, characterized in that, in order to simplify and increase the efficiency of the method, a series of materials are used as ceramic material (red clay, kaolin, monmorillonite, feldspar, illite, quartz. Or a mixture of them, and synthetic inorganic ion exchangers from the '<row'. titanate, niobate, zirconate, dioxide as an inorganic ion exchanger. zirconium or mixtures thereof, when mixing the ion exchanger with waste material with ceramic material, water is added to its content in a mixture of 23-27 wt.%, while the ratio of the number of ion exchanger with waste to the amount of ceramic material is 11-25%, annealing is carried out at normal pressure and at a temperature of 25 ceramicization of a mixture of a synthetic inorganic ion exchanger with waste and a ceramic material.
    [2]
    2. The method according to claim 1, characterized in that, in order to improve the binding of radioactive waste in the ceramic material, when mixing the components, vermiculite is additionally added to the mixture in an amount of 2 wt.%.
    类似技术:
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    同族专利:
    公开号 | 公开日
    EP0108759B1|1987-06-24|
    US4632778A|1986-12-30|
    JPH0452917B2|1992-08-25|
    FI821536A0|1982-04-30|
    FI71625B|1986-10-10|
    JPS59500685A|1984-04-19|
    WO1983003919A1|1983-11-10|
    FI71625C|1987-01-19|
    DE3372241D1|1987-07-30|
    EP0108759A1|1984-05-23|
    FI821536L|1983-10-31|
    SU1279541A1|1986-12-23|
    引用文献:
    公开号 | 申请日 | 公开日 | 申请人 | 专利标题
    DE559820C|1930-07-27|1932-09-24|Franco Bandini|Process for the production of ceramic molded bodies|
    US2616847A|1951-04-27|1952-11-04|William S Ginell|Disposal of radioactive cations|
    US3093593A|1958-07-14|1963-06-11|Coors Porcelain Co|Method for disposing of radioactive waste and resultant product|
    US3249551A|1963-06-03|1966-05-03|David L Neil|Method and product for the disposal of radioactive wastes|
    JPS5512560B2|1975-06-10|1980-04-02|
    DE2747951A1|1976-11-02|1978-05-11|Asea Ab|PROCESS FOR BINDING RADIOACTIVE SUBSTANCES IN A BODY THAT IS RESISTANT TO LEAKAGE BY WATER|
    SE410669B|1977-04-20|1979-10-22|Asea Ab|MAKE REMOVAL OF RADIOACTIVE MATERIAL|
    JPS6120839B2|1977-06-10|1986-05-23|Kerunfuorushungusutsuentorumu Kaarusuruue Gmbh|
    DE2726087C2|1977-06-10|1978-12-21|Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe|Process for the final disposal-ready, environmentally friendly solidification of "and moderately radioactive and / or actinide-containing, aqueous waste concentrates or of fine-grained solid waste suspended in water|
    DE2819085C3|1978-04-29|1981-04-23|Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe|Process for the environmentally friendly solidification of highly and moderately radioactive and / or actinide-containing aqueous waste concentrates or of fine-grain solid waste suspended in water in a manner that is ready for final disposal|
    JPS6132053B2|1980-01-16|1986-07-24|Kagaku Gijutsucho Mukizaishitsu Kenkyushocho|CA1282950C|1985-11-29|1991-04-16|Eric John Ramm|Vibratory processing arrangements|
    US4780239A|1986-05-22|1988-10-25|Westinghouse Electric Corp.|Ion exchange resin for immobilizing radioactive waste|
    JP3002525B2|1990-11-28|2000-01-24|株式会社日立製作所|Solidified radioactive waste and method of treating radioactive waste|
    US5733066A|1992-09-14|1998-03-31|Myers; Lawrence S.|Apparatus and method for disposal of nuclear and other hazardous wastes|
    US5302565A|1992-09-18|1994-04-12|Crowe General D|Ceramic container|
    DE19707982A1|1997-02-27|1998-09-03|Siemens Ag|Composition for long term storage of radioactive wastes|
    US5960368A|1997-05-22|1999-09-28|Westinghouse Savannah River Company|Method for acid oxidation of radioactive, hazardous, and mixed organic waste materials|
    US6329563B1|1999-07-16|2001-12-11|Westinghouse Savannah River Company|Vitrification of ion exchange resins|
    IL136685D0|2000-06-12|2001-06-14|Gribbitz Arthur|Process for treatment of radioactive waste|
    AU6831501A|2000-06-12|2001-12-24|Geomatrix Solutions Inc|Processes for immobilizing radioactive and hazardous wastes|
    US7550645B2|2004-02-23|2009-06-23|Geomatrix Solutions, Inc.|Process and composition for the immobilization of radioactive and hazardous wastes in borosilicate glass|
    WO2005084756A1|2004-02-23|2005-09-15|Geomatrix Solutions, Inc.|Process and composition for immobilization wastes in borosilicate glass|
    US8115044B2|2006-03-20|2012-02-14|Geomatrix Solutions, Inc.|Process and composition for the immobilization of high alkaline radioactive and hazardous wastes in silicate-based glasses|
    CZ20079A3|2007-01-02|2008-12-29|Ústav struktury a mechaniky hornin AV CR, v. v. i.|Solidification and stabilization of radioactive waste|
    JP6067497B2|2013-07-05|2017-01-25|株式会社東芝|Production method of solidified radioactive waste|
    法律状态:
    优先权:
    申请号 | 申请日 | 专利标题
    FI821536A|FI71625C|1982-04-30|1982-04-30|Process for ceramics of radioactive waste.|
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