Process for refining methacrylic acid
    1.
    发明授权
    Process for refining methacrylic acid 失效
    甲基丙烯酸精制方法

    公开(公告)号:US5959142A

    公开(公告)日:1999-09-28

    申请号:US550801

    申请日:1995-10-31

    CPC分类号: C07C51/44 C07C51/48

    摘要: A process for producing refined methacrylic acid comprising the steps of oxidizing methacrolein and the like catalytically in a vapor phase to form a methacrylic acid-containing gas, cooling and condensing the gas to an aqueous methacrylic acid solution, adding to the solution an organic solvent that forms two liquid phases with water to carry out an extraction operation and thereby to obtain an extract, bringing the extract into contact with water to mix them together, separating the mixture into an organic phase and a water phase, and distilling the organic phase. According to this process, highly refined methacrylic acid containing little dibasic acids such as maleic acid and citraconic acid can be obtained economically and without increasing wastes that are unrecoverable to the process.

    摘要翻译: 一种生产精制甲基丙烯酸的方法,包括在气相中催化氧化甲基丙烯醛等以形成含甲基丙烯酸的气体,将气体冷却并冷凝至甲基丙烯酸水溶液的步骤,向该溶液中加入有机溶剂, 与水形成两个液相以进行萃取操作,从而获得提取物,使提取物与水接触以将它们混合在一起,将混合物分离成有机相和水相,并蒸馏出有机相。 根据该方法,可以经济地获得含有少量二元酸如马来酸和柠康酸的高度精制的甲基丙烯酸,而不会增加不可回收的方法的废物。

    Zironium alloy for use in pressurized nuclear reactor fuel components
    7.
    发明授权
    Zironium alloy for use in pressurized nuclear reactor fuel components 失效
    用于加压核反应堆燃料组分的Zironium合金

    公开(公告)号:US5017336A

    公开(公告)日:1991-05-21

    申请号:US558797

    申请日:1990-07-26

    IPC分类号: C22C16/00 G21C3/07

    CPC分类号: G21C3/07 C22C16/00 Y02E30/40

    摘要: A zirconium alloy that has sufficient corrosion resistance, strength and stress relaxation property for use as a component of a pressurized water nuclear reactor fuel assembly is disclosed. This alloy consists essentially of 0.2 to 0.91% Sn, 0.18 to 0.6% Fe, 0.07 to 0.4% Cr, one or both of 0.05 to less than 0.5% and 0.01 to 0.2% Ta, one or both of 0.05 to 1% V and 0.05 to 1% Mo, with the balance being Zr and incidental impurities, all percentages being based on weight.

    摘要翻译: 公开了一种具有足够的耐腐蚀性,强度和应力松弛性能的锆合金,用作加压水核反应堆燃料组件的组分。 该合金基本上由Sn,0.2〜0.91%的Sn,0.18〜0.6%的Fe,0.07〜0.4%的Cr,0.05〜小于0.5%,0.01〜0.2%的Ta,0.05〜1%的V和1〜 0.05至1%的Mo,余量为Zr和杂质,所有百分数均以重量计。

    Zirconium alloy for use in spacer grids for nuclear reactor fuel
claddings
    9.
    发明授权
    Zirconium alloy for use in spacer grids for nuclear reactor fuel claddings 失效
    用于核反应堆燃料包层的隔离栅的锆合金

    公开(公告)号:US5019333A

    公开(公告)日:1991-05-28

    申请号:US419139

    申请日:1989-10-10

    IPC分类号: C22C16/00 G21C3/07 G21C3/34

    摘要: A zirconium alloy for use in spacer grids for nuclear reactor fuel claddings, which consists essentially of, on a weight percent basis,2.5 to 10% Nb,0.01 to 1.5% of one or more components selected from the group consisting of Y and rare earth elements and oxides thereof,0.05 to 1% of one or more optional element selected from the group consisting of Fe, Cr, Mo and V, andthe remainder Zr and incidental impurities.

    摘要翻译: 一种用于核反应堆燃料包层的间隔栅格的锆合金,其基本上由以重量百分数计,2.5至10%的Nb,0.01至1.5%的选自Y和稀土的一种或多种组分 元素和氧化物,0.05-1%选自Fe,Cr,Mo和V的一种或多种任选元素,余量为Zr和附带杂质。