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    • 1. 发明授权
    • Metals removal from spent salts
    • 从废盐中除去金属
    • US06436358B1
    • 2002-08-20
    • US09316485
    • 1999-05-21
    • Peter C. HsuErica H. Von HoltzDavid L. HippleLeslie J. SummersWilliam A. BrummondMartyn G. Adamson
    • Peter C. HsuErica H. Von HoltzDavid L. HippleLeslie J. SummersWilliam A. BrummondMartyn G. Adamson
    • C01G5600
    • C22B3/44C22B7/001C22B7/006Y02P10/214Y02P10/234
    • A method and apparatus for removing metal contaminants from the spent salt of a molten salt oxidation (MSO) reactor is described. Spent salt is removed from the reactor and analyzed to determine the contaminants present and the carbonate concentration. The salt is dissolved in water, and one or more reagents may be added to precipitate the metal oxide and/or the metal as either metal oxide, metal hydroxide, or as a salt. The precipitated materials are filtered, dried and packaged for disposal as waste or can be immobilized as ceramic pellets. More than about 90% of the metals and mineral residues (ashes) present are removed by filtration. After filtration, salt solutions having a carbonate concentration >20% can be spray-dried and returned to the reactor for re-use. Salt solutions containing a carbonate concentration
    • 描述了从熔融盐氧化(MSO)反应器的废盐中除去金属污染物的方法和设备。 将废盐从反应器中取出并分析以确定存在的污染物和碳酸盐浓度。 将盐溶解在水中,并且可以加入一种或多种试剂以将金属氧化物和/或金属以金属氧化物,金属氢氧化物或盐形式沉淀。 将沉淀的材料过滤,干燥并包装以作为废物处理,或者可以固定为陶瓷颗粒。 通过过滤除去存在的金属和矿物质残余物(灰分)超过约90%。 过滤后,碳酸盐浓度> 20%的盐溶液可以喷雾干燥并返回反应器再次使用。 含有碳酸盐浓度<20%的盐溶液需要使用离子交换柱进一步清理,该离子交换柱产生含有小于1.0ppm污染物的盐溶液。
    • 2. 发明授权
    • Actinide removal from spent salts
    • 从废盐中除去锕系元素
    • US06471922B1
    • 2002-10-29
    • US09259784
    • 1999-03-01
    • Peter C. HsuErica H. von HoltzDavid L. HippleLeslie J. SummersMartyn G. Adamson
    • Peter C. HsuErica H. von HoltzDavid L. HippleLeslie J. SummersMartyn G. Adamson
    • C01G5600
    • C22B7/006C22B3/44C22B7/001Y02P10/214Y02P10/234
    • A method for removing actinide contaminants (uranium and thorium) from the spent salt of a molten salt oxidation (MSO) reactor is described. Spent salt is removed from the reactor and analyzed to determine the contaminants present and the carbonate concentration. The salt is dissolved in water, and one or more reagents are added to precipitate the thorium as thorium oxide and/or the uranium as either uranium oxide or as a diuranate salt. The precipitated materials are filtered, dried and packaged for disposal as radioactive waste. About 90% of the thorium and/or uranium present is removed by filtration. After filtration, salt solutions having a carbonate concentration >20% can be dried and returned to the reactor for re-use. Salt solutions containing a carbonate concentration
    • 描述了从熔融盐氧化(MSO)反应器的废盐中除去锕系污染物(铀和钍)的方法。 将废盐从反应器中取出并分析以确定存在的污染物和碳酸盐浓度。 将盐溶解在水中,并加入一种或多种试剂以将钍氧化为钍氧化物和/或铀作为氧化铀或作为二铀酸盐沉淀。 将沉淀的材料过滤,干燥并包装以作为放射性废物处理。 通过过滤除去约90%的钍和/或铀。 过滤后,可以将碳酸盐浓度> 20%的盐溶液干燥并返回反应器再次使用。 含有碳酸盐浓度<20%的盐溶液需要使用离子交换柱进一步清理,产生含有小于0.1ppm钍或铀的盐溶液。