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Final storage of radioactive scrap by vitrification - where liq. scrap contg. borates is converted into lead borate or borosilicate glass

机译:通过玻璃化法最终保存放射性废料-液位。废料续硼酸盐转化为硼酸铅或硼硅酸盐玻璃

摘要

Liq. scrap concentrates contg. borates, and with weak to medium radioactivity, are mixed with glass-making addns. using a max. ratio of 1:3. The mixt. is then heated to obtain a vitrifiable melt. Prior to the mixing operation, the liq. concentrates are pref. pre-dried to max. 5% residual moisture. Concentrates contg. B are pref. mixed with (1) 70 wt.% lead oxide, and melted at ca 600 deg.C. to obtain a lead borate glass; or (b) 50 wt.% silicates, esp. clay, and heated at ca 1000 deg.C to make a borosilicate glass. In either case (a,b), direct electric resistance heating is pref. used. Ion exchange resins contg. radioactive ions can be included in the mixt. Used esp. with scrap obtd. from pressurised water nuclear reactors, where 10 t/year of scrap can be obtd.
机译:酒废料浓缩续将具有弱至中等放射性的硼酸盐与玻璃制造添加剂混合。使用最大比例为1:3。混音。然后加热,得到可玻璃化的熔体。在混合操作之前,液体。精矿是首选。预干燥至最大5%残留水分。集中。 B是首选。与(1)70 wt。%的氧化铅混合,并在约600℃熔化。获得硼酸铅玻璃;或(b)50重量%的硅酸盐,尤其是粘土,并在约1000℃下加热制成硼硅酸盐玻璃。在任一情况下(a,b),直接电阻加热都是优选的。用过的。离子交换树脂续混合物中可以包含放射性离子。二手的与废料。来自压水核反应堆,在那里可以废掉10吨/年的废料。

著录项

  • 公开/公告号DE3026968A1

    专利类型

  • 公开/公告日1982-02-04

    原文格式PDF

  • 申请/专利权人 KRAFTWERK UNION AG;

    申请/专利号DE19803026968

  • 发明设计人 PUTHAWALAANWERDIPL.-ING.;BEGEDIETMAR;

    申请日1980-07-16

  • 分类号G21F9/16;

  • 国家 DE

  • 入库时间 2022-08-22 12:43:09

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