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    • 42. 发明授权
    • Use of ion conductors in the pyrochemical reduction of oxides
    • 在化学还原氧化物中使用离子导体
    • US5282937A
    • 1994-02-01
    • US994786
    • 1992-12-22
    • William E. MillerZygmunt Tomczuk
    • William E. MillerZygmunt Tomczuk
    • C25C3/02C25C3/34
    • C25C3/02C25C3/34Y10S204/04
    • An electrochemical process and electrochemical cell for reducing a metal oxide are provided. First the oxide is separated as oxygen gas using, for example, a ZrO.sub.2 oxygen ion conductor anode and the metal ions from the reduction salt are reduced and deposited on an ion conductor cathode, for example, sodium ion reduced on a .beta.-alumina sodium ion conductor cathode. The generation of and separation of oxygen gas avoids the problem with chemical back reaction of oxygen with active metals in the cell. The method also is characterized by a sequence of two steps where an inert cathode electrode is inserted into the electrochemical cell in the second step and the metallic component in the ion conductor is then used as the anode to cause electrochemical reduction of the metal ions formed in the first step from the metal oxide where oxygen gas formed at the anode. The use of ion conductors serves to isolate the active components from chemically reacting with certain chemicals in the cell. While applicable to a variety of metal oxides, the invention has special importance for reducing CaO to Ca.degree. used for reducing UO.sub.2 and PuO.sub.2 to U and Pu.
    • 提供了用于还原金属氧化物的电化学工艺和电化学电池。 首先,使用例如ZrO 2氧离子导体阳极将氧化物分离为氧气,并且来自还原盐的金属离子被还原并沉积在离子导体阴极上,例如在(β) - 氧化铝上还原的钠离子 钠离子导体阴极。 氧气的产生和分离避免了电池中氧与活性金属的化学反应的问题。 该方法的特征还在于在第二步骤中将惰性阴极插入电化学电池中的两个步骤的顺序,然后将离子导体中的金属组分用作阳极,以使电解还原形成的金属离子 在阳极处形成氧气的金属氧化物的第一步。 使用离子导体用于隔离活性组分与细胞中某些化学物质的化学反应。 当适用于各种金属氧化物时,本发明特别重要的是将用于将UO 2和PuO 2还原成U和Pu的CaO降低至Ca度。
    • 43. 发明授权
    • Electrostatic discharge detection and clamp control circuit
    • 静电放电检测和钳位控制电路
    • US5255146A
    • 1993-10-19
    • US752036
    • 1991-08-29
    • William E. Miller
    • William E. Miller
    • H01L27/04H01L21/822H02H9/04
    • H02H9/046
    • A switching element is connected to an integrated circuit for shunting an ESD pulse away from the integrated circuit features. A plurality of detection circuits responsive to typical ESD waveform characteristics provide logical control of the switching means. In the preferred embodiment, a NAND gate drives the switching element. The first input to the NAND gate is a first RC network having a first time constant that exceeds the characteristic rise time of the typical ESD pulse, but not the characteristic duration of the typical ESD pulse. The second input to the NAND gate is a feedback loop from the NAND gate output. The feedback loop includes a second RC network having a second time constant that exceeds the duration of a noise pulse, a third RC network having a third time constant that approximates the characteristic duration of the typical ESD pulse, and an inverter between the second and third RC networks. Application of the ESD pulse causes the first input to drive the NAND gate, thus turning on the switching element, and if the ESD pulse is still present when the second time constant is exceeded, the switching means is latched on via the second input until the third time constant is exceeded.
    • 44. 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。
    • 45. 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。