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    • 1. 发明授权
    • Magnesium transport extraction of transuranium elements from LWR fuel
    • 镁离子从LWR燃料中提取超铀元素
    • US5147616A
    • 1992-09-15
    • US770387
    • 1991-10-03
    • John P. AckermanJames E. BattlesTerry R. JohnsonWilliam E. MillerR. Dean Pierce
    • John P. AckermanJames E. BattlesTerry R. JohnsonWilliam E. MillerR. Dean Pierce
    • C22B60/02G21C19/48
    • C22B60/0213G21C19/48Y02P10/212Y02W30/884
    • A process of separating transuranium actinide values from uranium values present in spent nuclear oxide fuels which contain rare earth and noble metal fission products. The oxide fuel is reduced with Ca metal in the presence of CaCl.sub.2 and a U-Fe alloy containing not less than about 84% by weight uranium at a temperature in the range of from about 800.degree. C. to about 850.degree. C. to produce additional uranium metal which dissolves in the U-Fe alloy raising the uranium concentration and having transuranium actinide metals and rare earth fission product metals and the noble metal fission products dissolved therein. The CaCl.sub.2 having CaO and fission products of alkali metals and the alkali earth metals and iodine dissolved therein is separated and electrolytically treated with a carbon electrode to reduce the CaO to Ca metal while converting the carbon electrode to CO and CO.sub.2. The Ca metal and CaCl.sub.2 is recycled to reduce additional oxide fuel. The U-Fe alloy having transuranium actinide metals and rare earth fission product metals and the noble metal fission products dissolved therein is contacted with Mg metal which takes up the actinide and rare earth fission product metals. The U-Fe alloy retains the noble metal fission products and is stored while the Mg is distilled and recycled leaving the transuranium actinide and rare earth fission products isolated.
    • 将铀的锕系元素值与含有稀土和贵金属裂变产物的废核氧化物燃料中存在的铀值分离的过程。 在CaCl 2和含有不少于约84重量%铀的U-Fe合金的存在下,在约800℃至约850℃的温度范围内,氧化物燃料用Ca金属还原以产生 溶解在U-Fe合金中的另外的铀金属提高铀浓度并且具有铀锕系金属和稀土裂变产物金属以及其中溶解的贵金属裂变产物。 将碳酸钙和碱金属的裂变产物和碱土金属和碘溶解在其中的CaCl 2分离并用碳电极进行电解处理,以将碳电极转化为CO和CO 2,从而将CaO还原为Ca金属。 Ca金属和CaCl2被再循环以减少额外的氧化物燃料。 具有锕系金属和稀土裂变产物金属的U-Fe合金和溶解在其中的贵金属裂变产物与吸收锕系元素和稀土裂变产物金属的金属Mg接触。 U-Fe合金保留贵金属裂变产物,并在Mg蒸馏和再循环时储存,分离出铀锕系和稀土裂变产物。
    • 3. 发明授权
    • Salt transport extraction of transuranium elements from lwr fuel
    • 从lwr燃料中提取超铀元素
    • US5160367A
    • 1992-11-03
    • US770385
    • 1991-10-03
    • R. Dean PierceJohn P. AckermanJames E. BattlesTerry R. JohnsonWilliam E. Miller
    • R. Dean PierceJohn P. AckermanJames E. BattlesTerry R. JohnsonWilliam E. Miller
    • C22B60/02G21C19/48
    • C22B60/0213G21C19/48Y02P10/212Y02W30/884
    • A process of separating transuranium actinide values from uranium values present in spent nuclear oxide fuels which contain rare earth and noble metal fission products. The oxide fuel is reduced with Ca metal in the presence of CaCl.sub.2 and a Cu--Mg alloy containing not less than about 25% by weight Mg at a temperature in the range of from about 750.degree. C. to about 850.degree. C. to precipitate uranium metal and some of the noble metal fission products leaving the Cu--Mg alloy having transuranium actinide metals and rare earth fission product metals and some of the noble metal fission products dissolved therein. The CaCl.sub.2 having CaO and fission products of alkali metals and the alkali earth metals and iodine dissolved therein is separated and electrolytically treated with a carbon electrode to reduce the CaO to Ca metal while converting the carbon electrode to CO and CO.sub.2. The Ca metal and CaCl.sub.2 is recycled to reduce additional oxide fuel. The Cu--Mg alloy having transuranium metals and rare earth fission product metals and the noble metal fission products dissolved therein is contacted with a transport salt including Mg Cl.sub.2 to transfer Mg values from the transport salt to the Cu--Mg alloy while transuranium actinide and rare earth fission product metals transfer from the Cu--Mg alloy to the transport salt. Then the transport salt is mixed with a Mg--Zn alloy to transfer Mg values from the alloy to the transport salt while the transuranium actinide and rare earth fission product values dissolved in the salt are reduced and transferred to the Mg--Zn alloy.
    • 将铀的锕系元素值与含有稀土和贵金属裂变产物的废核氧化物燃料中存在的铀值分离的过程。 在CaCl 2和Cu-Mg合金的存在下,在约750℃至约850℃的温度范围内,氧化物燃料用Ca金属还原,其含有不低于约25重量%的Mg,以沉淀 铀金属和一些离开Cu-Mg合金的贵金属裂变产物具有铀钛锕金属和稀土裂变产物金属以及一些溶解在其中的贵金属裂变产物。 将碳酸钙和碱金属的裂变产物和碱土金属和碘溶解在其中的CaCl 2分离并用碳电极进行电解处理,以将碳电极转化为CO和CO 2,从而将CaO还原为Ca金属。 Ca金属和CaCl2被再循环以减少额外的氧化物燃料。 将具有锇金属和稀土裂变产物金属的Cu-Mg合金以及溶解在其中的贵金属裂变产物与包含Mg Cl 2的运输盐接触,以将Mg值从运输盐转移到Cu-Mg合金,同时穿过锕系和稀有金属 土壤裂变产物金属从Cu-Mg合金转移到运输盐。 然后将输送盐与Mg-Zn合金混合,将Mg值从合金转移到运输盐,同时溶解在盐中的铀锕系和稀土裂变产物值被还原并转移到Mg-Zn合金中。
    • 4. 发明授权
    • Uranium chloride extraction of transuranium elements from LWR fuel
    • 氯化铀从LWR燃料中提取超铀元素
    • US5141723A
    • 1992-08-25
    • US770386
    • 1991-10-03
    • William E. MillerJohn P. AckermanJames E. BattlesTerry R. JohnsonR. Dean Pierce
    • William E. MillerJohn P. AckermanJames E. BattlesTerry R. JohnsonR. Dean Pierce
    • C22B60/02G21C19/48
    • G21C19/48C22B60/0213Y02W30/884
    • A process of separating transuranium actinide values from uranium values present in spent nuclear oxide fuels containing rare earth and noble metal fission products as well as other fission products is disclosed. The oxide fuel is reduced with Ca metal in the presence of Ca chloride and a U-Fe alloy which is liquid at about 800.degree. C. to dissolve uranium metal and the noble metal fission product metals and transuranium actinide metals and rare earth fission product metals leaving Ca chloride having CaO and fission products of alkali metals and the alkali earth metals and iodine dissolved therein. The Ca chloride and CaO and the fission products contained therein are separated from the U-Fe alloy and the metal values dissolved therein. The U-Fe alloy having dissolved therein reduced metals from the spent nuclear fuel is contacted with a mixture of one or more alkali metal or alkaline earth metal halides selected from the class consisting of alkali metal or alkaline earth metal and Fe or U halide or a combination thereof to transfer transuranium actinide metals and rare earth metals to the halide salt leaving the uranium and some noble metal fission products in the U-Fe alloy and thereafter separating the halide salt and the transuranium metals dissolved therein from the U-Fe alloy and the metals dissolved therein.
    • 公开了将铀的锕系元素值与含有稀土和贵金属裂变产物以及其它裂变产物的废核氧化物燃料中存在的铀值分离的方法。 在氯化钙和U-Fe合金存在下,氧化物燃料在大约800℃下液化,以溶解铀金属和贵金属裂变产物金属和铀锕系金属和稀土裂变产物金属 留下具有CaO的氯化钙和碱金属的裂变产物和溶解在其中的碱土金属和碘。 其中所含的氯化钙和CaO及其裂变产物与U-Fe合金分离,金属溶解在其中。 其中溶解有来自废核燃料的还原金属的U-Fe合金与一种或多种选自碱金属或碱土金属和Fe或U卤化物的碱金属或碱土金属卤化物的混合物接触,或者 其组合将铀锕系金属和稀土金属转移到离开铀的卤化物盐和U-Fe合金中的一些贵金属裂变产物,然后从U-Fe合金中分离卤化物盐和溶解在其中的铀钛金属, 金属溶解在其中。
    • 7. 发明授权
    • U+4 generation in HTER
    • U + 4代
    • US07011736B1
    • 2006-03-14
    • US10637089
    • 2003-08-05
    • William E. MillerEddie C. GayZygmunt Tomczuk
    • William E. MillerEddie C. GayZygmunt Tomczuk
    • C25C3/34
    • C25C3/34C25C7/005
    • A improved device and process for recycling spent nuclear fuels, in particular uranium metal, that facilitates the refinement and recovery of uranium metal from spent metallic nuclear fuels. The electrorefiner device comprises two anodes in predetermined spatial relation to a cathode. The anodese have separate current and voltage controls. A much higher voltage than normal for the electrorefining process is applied to the second anode, thereby facilitating oxidization of uranium (III), U+, to uranium (IV), U+4. The current path from the second anode to the cathode is physically shorter than the similar current path from the second anode to the spent nuclear fuel contained in a first anode shaped as a basket. The resulting U+4 oxidizes and solubilizes rough uranium deposited on the surface of the cathode. A softer uranium metal surface is left on the cathode and is more readily removed by a scraper.
    • 用于回收废核燃料,特别是铀金属的改进装置和方法,其有助于从废金属核燃料中精炼和回收铀金属。 电学纯化装置包括与阴极预定的空间关系的两个阳极。 阳极电池具有单独的电流和电压控制。 对于第二阳极施加比正常电压高的电解精炼工艺,因此铀(III),铀(Ⅳ),铀(Ⅳ),U + 4, SUP>。 从第二阳极到阴极的电流路径物理上短于从第二阳极到包含在形成为篮状物的第一阳极中的废核燃料的类似电流路径。 所产生的U + 4氧化并溶解沉积在阴极表面上的粗铀。 较软的铀金属表面留在阴极上,更容易被刮刀去除。