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1. 发明授权

US5147616A Magnesium transport extraction of transuranium elements from LWR fuel 失效
标题翻译：镁离子从LWR燃料中提取超铀元素
公开(公告)号：US5147616A
公开(公告)日：1992-09-15
申请号：US770387
申请日：1991-10-03
申请人： John P. Ackerman , James E. Battles , Terry R. Johnson , William E. Miller , R. Dean Pierce
发明人： John P. Ackerman , James E. Battles , Terry R. Johnson , William E. Miller , R. Dean Pierce
IPC分类号： C22B60/02 , G21C19/48
CPC分类号： C22B60/0213 , G21C19/48 , Y02P10/212 , Y02W30/884
摘要： 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.
摘要翻译：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。

2. 发明授权

US5160367A Salt transport extraction of transuranium elements from lwr fuel 失效
标题翻译：从lwr燃料中提取超铀元素
公开(公告)号：US5160367A
公开(公告)日：1992-11-03
申请号：US770385
申请日：1991-10-03
申请人： R. Dean Pierce , John P. Ackerman , James E. Battles , Terry R. Johnson , William E. Miller
发明人： R. Dean Pierce , John P. Ackerman , James E. Battles , Terry R. Johnson , William E. Miller
IPC分类号： C22B60/02 , G21C19/48
CPC分类号： C22B60/0213 , G21C19/48 , Y02P10/212 , Y02W30/884
摘要： 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.
摘要翻译：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。

3. 发明授权

US5141723A Uranium chloride extraction of transuranium elements from LWR fuel 失效
标题翻译：氯化铀从LWR燃料中提取超铀元素
公开(公告)号：US5141723A
公开(公告)日：1992-08-25
申请号：US770386
申请日：1991-10-03
申请人： William E. Miller , John P. Ackerman , James E. Battles , Terry R. Johnson , R. Dean Pierce
发明人： William E. Miller , John P. Ackerman , James E. Battles , Terry R. Johnson , R. Dean Pierce
IPC分类号： C22B60/02 , G21C19/48
CPC分类号： G21C19/48 , C22B60/0213 , Y02W30/884
摘要： 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.
摘要翻译：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。

4. 发明授权

US4814046A Process to separate transuranic elements from nuclear waste 失效
标题翻译：将超铀元素与核废料分开的过程
公开(公告)号：US4814046A
公开(公告)日：1989-03-21
申请号：US217916
申请日：1988-07-12
申请人： Terry R. Johnson , John P. Ackerman , Zygmunt Tomczuk , Donald F. Fischer
发明人： Terry R. Johnson , John P. Ackerman , Zygmunt Tomczuk , Donald F. Fischer
IPC分类号： G21C19/44 , C01G56/00 , C22B60/02 , C22B60/04 , G21C19/48 , G21F9/06 , G21F9/30 , C01G57/00 , G21C1/24 , G21C19/42
CPC分类号： C22B60/04 , C22B60/0295 , G21C19/48 , Y02W30/884
摘要： A process for removing transuranic elements from a waste chloride electrolytic salt containing transuranic elements in addition to rare earth and other fission product elements so the salt waste may be disposed of more easily and the valuable transuranic elements may be recovered for reuse. The salt is contacted with a cadmium-uranium alloy which selectively extracts the transuranic elements from the salt. The waste salt is generated during the reprocessing of nuclear fuel associated with the Integral Fast Reactor (IFR).
摘要翻译：除了稀土和其他裂变产物元素之外，还可以从含有超铀元素的废氯化物电解盐中除去超铀元素的方法，因此可以更容易地处理盐废物，并且可以回收有价值的超铀元素以便再利用。盐与选择性地从盐中提取超铀元素的镉 - 铀合金接触。在与Integral Fast Reactor（IFR）相关的核燃料的后处理中产生废盐。

5. 发明授权

US5336450A Process to remove rare earth from IFR electrolyte 失效
标题翻译：从IFR电解液中除去稀土的工艺
公开(公告)号：US5336450A
公开(公告)日：1994-08-09
申请号：US999339
申请日：1992-12-31
申请人： John P. Ackerman , Terry R. Johnson
发明人： John P. Ackerman , Terry R. Johnson
IPC分类号： C22B61/00 , G21C19/48 , G21F9/00
CPC分类号： C22B61/00 , G21C19/48 , Y02W30/884
摘要： The invention is a process for the removal of rare earths from molten chloride electrolyte salts used in the reprocessing of integrated fast reactor fuel (IFR). The process can be used either continuously during normal operation of the electrorefiner or as a batch process. The process consists of first separating the actinide values from the salt before purification by removal of the rare earths. After replacement of the actinides removed in the first step, the now-purified salt electrolyte has the same uranium and plutonium concentration and ratio as when the salt was removed from the electrorefiner.
摘要翻译：本发明是从用于综合快堆反应堆燃料（IFR）后处理的氯化氯电解质盐中除去稀土的方法。该方法可以在电抛光机的正常操作期间连续使用或作为间歇工艺使用。该方法包括首先通过除去稀土元素将纯化前的锕系元素值与盐分离。在更换在第一步骤中除去的锕系元素后，现有纯化的盐电解质具有与从电学纯化器中除去盐时相同的铀和钚浓度和比例。

6. 发明授权

US4880506A Electrorefining process and apparatus for recovery of uranium and a mixture of uranium and plutonium from spent fuels 失效
标题翻译：用于从废燃料中回收铀和铀和钚的混合物的电解精炼工艺和设备
公开(公告)号：US4880506A
公开(公告)日：1989-11-14
申请号：US117880
申请日：1987-11-05
申请人： John P. Ackerman , William E. Miller
发明人： John P. Ackerman , William E. Miller
IPC分类号： G21C19/46 , C25C3/34 , C25C7/00 , G21C19/44 , G21C19/48
CPC分类号： C25C7/005 , C25C3/34 , G21C19/48 , Y02W30/884
摘要： An electrorefining process and apparatus for the recovery of uranium and a mixture of uranium and plutonium from spent fuel using an electrolytic cell having a lower molten cadmium pool containing spent nuclear fuel, an intermediate electrolyte pool, an anode basket containing spent fuel, and two cathodes, the first cathode composed of either a solid alloy or molten cadmium and the second cathode composed of molten cadmium. Using this cell, additional amounts of uranium and plutonium from the anode basket are dissolved in the lower molten cadmium pool, and then substantially pure uranium is electrolytically transported and deposited on the first alloy or molten cadmium cathode. Subsequently, a mixture of uranium and plutonium is electrotransported and deposited on the second molten cadmium cathode.
摘要翻译：一种用于使用具有含有乏核燃料的较低熔融镉池的电解池，中间电解池，含有废燃料的阳极筐和两个阴极从废燃料中回收铀和铀和钚的混合物的电解精炼方法和装置，由固体合金或熔融镉构成的第一阴极和由熔融镉组成的第二阴极。使用该电池，将来自阳极筐的额外量的铀和钚溶解在下部熔融镉池中，然后将基本上纯的铀电解输送并沉积在第一合金或熔融镉阴极上。随后，将铀和钚的混合物电运输并沉积在第二熔融镉阴极上。

7. 发明授权

US07638026B1 Uranium dioxide electrolysis 失效
标题翻译：二氧化铀电解
公开(公告)号：US07638026B1
公开(公告)日：2009-12-29
申请号：US11215202
申请日：2005-08-24
申请人： James L. Willit , John P. Ackerman , Mark A. Williamson
发明人： James L. Willit , John P. Ackerman , Mark A. Williamson
IPC分类号： C25C3/34
CPC分类号： C25C3/34
摘要： This is a single stage process for treating spent nuclear fuel from light water reactors. The spent nuclear fuel, uranium oxide, UO2, is added to a solution of UCl4 dissolved in molten LiCl. A carbon anode and a metallic cathode is positioned in the molten salt bath. A power source is connected to the electrodes and a voltage greater than or equal to 1.3 volts is applied to the bath. At the anode, the carbon is oxidized to form carbon dioxide and uranium chloride. At the cathode, uranium is electroplated. The uranium chloride at the cathode reacts with more uranium oxide to continue the reaction. The process may also be used with other transuranic oxides and rare earth metal oxides.
摘要翻译：这是从轻水反应堆处理乏核燃料的单阶段过程。将废核燃料，氧化铀，UO2加入到溶解在熔融LiCl中的UCl 4溶液中。碳阳极和金属阴极位于熔融盐浴中。电源连接到电极，并且将大于或等于1.3伏的电压施加到电镀槽。在阳极处，碳被氧化形成二氧化碳和氯化铀。在阴极处，铀被电镀。阴极处的铀氯化物与更多的氧化铀反应以继续反应。该方法也可以与其他超铀氧化物和稀土金属氧化物一起使用。

8. 发明授权

US07410561B2 Three-electrode metal oxide reduction cell 有权
标题翻译：三电极金属氧化物还原电池
公开(公告)号：US07410561B2
公开(公告)日：2008-08-12
申请号：US11084940
申请日：2005-03-21
申请人： Dennis W. Dees , John P. Ackerman
发明人： Dennis W. Dees , John P. Ackerman
IPC分类号： C25C5/04 , C25C3/34
CPC分类号： C25C3/00 , C25C3/34
摘要： A method of electrochemically reducing a metal oxide to the metal in an electrochemical cell is disclosed along with the cell. Each of the anode and cathode operate at their respective maximum reaction rates. An electrolyte and an anode at which oxygen can be evolved, and a cathode including a metal oxide to be reduced are included as is a third electrode with independent power supplies connecting the anode and the third electrode and the cathode and the third electrode.
摘要翻译：与电池一起公开了一种在电化学电池中电化学还原金属氧化物到金属的方法。阳极和阴极中的每一个以它们各自的最大反应速率操作。包括能够放出氧的电解质和阳极以及包含待还原的金属氧化物的阴极，包括连接阳极和第三电极以及阴极和第三电极的独立电源的第三电极。

9. 发明授权

US5096545A Plutonium recovery from spent reactor fuel by uranium displacement 失效
标题翻译：铀从废反应堆燃料中钚回收
公开(公告)号：US5096545A
公开(公告)日：1992-03-17
申请号：US703641
申请日：1991-05-21
申请人： John P. Ackerman
发明人： John P. Ackerman
IPC分类号： C22B60/02 , C22B60/04 , C25C3/34 , G21C19/48
CPC分类号： C25C3/34 , C22B60/0213 , C22B60/04 , G21C19/48 , Y02W30/884
摘要： A process for separating uranium values and transuranic values from fission products containing rare earth values when the values are contained together in a molten chloride salt electrolyte. A molten chloride salt electrolyte with a first ratio of plutonium chloride to uranium chloride is contacted with both a solid cathode and an anode having values of uranium and fission products including plutonium. A voltage is applied across the anode and cathode electrolytically to transfer uranium and plutonium from the anode to the electrolyte while uranium values in the electrolyte electrolytically deposit as uranium metal on the solid cathode in an amount equal to the uranium and plutonium transferred from the anode causing the electrolyte to have a second ratio of plutonium chloride to uranium chloride. Then the solid cathode with the uranium metal deposited thereon is removed and molten cadmium having uranium dissolved therein is brought into contact with the electrolyte resulting in chemical transfer of plutonium values from the electrolyte to the molten cadmium and transfer of uranium values from the molten cadmium to the electrolyte until the first ratio of plutonium chloride to uranium chloride is reestablished.
摘要翻译：当将这些值包含在熔融氯化物盐电解质中时，从含有稀土值的裂变产物中分离铀值和超铀值的方法。将具有钚氯化物与铀氯化物的第一比例的熔融氯化物盐电解质与具有铀和裂变产物（包括钚）的值的固体阴极和阳极接触。在阳极和阴极电解施加电压以将铀和钚从阳极转移到电解质，而电解质中的铀值电解沉积为固体阴极上的铀金属，其数量等于从阳极转移的铀和钚，导致电解质具有钚氯化物与铀氯化物的第二比例。然后去除沉积在其上的铀金属的固体阴极，使溶解有铀的熔融镉与电解液接触，导致钚值从电解质向熔融镉的化学转移，并将铀值从熔融镉转移到电解液直到钚氯化物与氯化铀的第一比例重新建立。

10. 发明授权

US4499663A Method of fabricating a monolithic core for a solid oxide fuel cell 失效
标题翻译：制造固体氧化物燃料电池的整体式核心的方法
公开(公告)号：US4499663A
公开(公告)日：1985-02-19
申请号：US541184
申请日：1983-10-12
申请人： Stanley A. Zwick , John P. Ackerman
发明人： Stanley A. Zwick , John P. Ackerman
IPC分类号： H01M8/12 , H01M8/10
CPC分类号： H01M8/1213 , H01M4/9033 , H01M4/9066 , Y10T29/49108
摘要： A method is disclosed for forming a core for use in a solid oxide fuel cell that electrochemically combines fuel and oxidant for generating galvanic output. The core has an array of electrolyte and interconnect walls that are substantially devoid of any composite inert materials for support consisting instead only of the active anode, cathode, electrolyte and interconnect materials. Each electrolyte wall consists of cathode and anode materials sandwiching electrolyte material therebetween, and each interconnect wall consists of the cathode and anode materials sandwiching interconnect material therebetween. The electrolyte and interconnect walls define a plurality of substantially parallel core passageways alternately having respectively the inside faces thereof with only the anode material or with only the cathode material exposed. In the wall structure, the electrolyte and interconnect materials are only 0.002-0.01 cm thick; and the cathode and anode materials are only 0.002-0.05 cm thick. The method consists of building up the electrolyte and interconnect walls by depositing each material on individually and endwise of the wall itself, where each material deposit is sequentially applied for one cycle; and where the depositing cycle is repeated many times until the material buildup is sufficient to formulate the core. The core is heat cured to become dimensionally and structurally stable.
摘要翻译：公开了一种用于形成用于固体氧化物燃料电池的芯的方法，其中电化学地组合燃料和氧化剂以产生电流输出。核心具有基本上不含任何用于支持的复合惰性材料的电解质和互连壁阵列，而仅包括活性阳极，阴极，电解质和互连材料。每个电解质壁由在其间夹有电解质材料的阴极和负极材料组成，并且每个互连壁由在其间夹置互连材料的阴极和阳极材料组成。电解质和互连壁限定了多个基本上平行的芯通道，其交替地分别具有其内表面仅具有阳极材料或仅露出阴极材料。在壁结构中，电解质和互连材料只有0.002-0.01厘米厚; 阴极和阳极材料的厚度只有0.002-0.05厘米。该方法包括通过在墙壁本身的单独和最终方向上沉积每种材料来建立电解质和互连壁，其中每个材料沉积物依次施加一个周期; 并且沉积周期重复多次，直到材料堆积足以配制核心。核心被热固化成尺寸和结构稳定。

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