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1.发明授权Ruthenium decontamination of solutions derived from the processing of irradiated fuels 失效从加工燃料中得到的解决方案的二氧化碳去除
公开(公告)号：US3853980A
公开(公告)日：1974-12-10
申请号：US22424172
申请日：1972-02-07
Applicant: COMMISSARIAT ENERGIE ATOMIQUE
Inventor： BERTON Y , FERNANDEZ N , CHAUVET P , CLAPIT S
CPC classification number: G21F9/10
Abstract: The method consists in adding ferrous ions and cupric ions to the solution arising from the processing of irradiated fuels after the solution has first been put into contact if necessary with a quantity of oxidizing agent which is just sufficient to destroy in the raw effluent any substance having a potential oxidizing action on the iron which is intended to remain in the ferrous state, in rendering the solution alkaline in order to precipitate the corresponding compounds of copper and of iron, and in coagulating and filtering the slurries obtained.
Abstract translation: 该方法包括在溶液首先被接触之后，如果需要与一定数量的氧化剂接触，在处理照射的燃料中产生的溶液中加入亚铁离子和铜离子，该氧化剂足以在生流出物中破坏任何具有 意图保持在亚铁状态的铁的潜在的氧化作用，使溶液呈碱性，以便沉淀出相应的铜和铁的化合物，以及凝结和过滤所获得的浆料。
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公开(公告)号：US3840365A
公开(公告)日：1974-10-08
申请号：US18402971
申请日：1971-09-27
CPC classification number: C22B15/0078 , C22B3/04 , C22B15/0065 , C22B15/0069 , C22B15/0071 , C22B15/0073 , C22B15/008 , C22B15/0091 , Y02P10/234 , Y02P10/236
Abstract: The disclosure is of a process for recovery of metals, including copper and, where present in sufficient quantities, uranium, gold, and silver, from ores. According to the process, the ores are leached and the recovered metals are deposited on metal sheets, particularly on sheets of iron or aluminum. The metals to be recovered are leached from the ore by highly buffered leach solutions of controlled pH in the range of 2 to 4.
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3.发明授权Method of precipitating americium oxide from a mixture of americium and plutonium metals in a fused salt bath containing puo2 失效在含有PUO2的熔融盐浴中从美国和普通金属混合物中预处理氧化铝的方法
公开(公告)号：US3804939A
公开(公告)日：1974-04-16
申请号：US26505572
申请日：1972-06-21
Applicant: ATOMIC ENERGY COMMISSION
Inventor： STRICKLAND W , AUGE R , BROWN J
CPC classification number: C22B60/0295 , C01G56/009
Abstract: METHOD OF RECOVERING AMERICIUM FROM PLUTONIUM METAL SOURCE MATERIAL WHICH CONTAINS AMERICIUM COMPRISING CONTACTING MOLTEN PLUTONIUM METAL SOURCE MATERIAL WITH AN ABOUT EUAL WEIGHTS OF MOLTEN EQUIMOLAR SALT MIXTURE OF SODIUM CHLORIDE AND POTASSIUM CHLORIDE CONTAINING NOT GREATER THAN ABOUT 25 WEIGHT PERCENT (W/O) PLUTONIUM OXIDE AS REDUCTANT TO CONVERT THE AMERICIUM TO AMERICIUM OXIDE, THEREAFTER SEPARATING THE SALT MIXTURE CONTAINING THE AMERICIUM OXIDE FROM THE PLUTONIUM AND SUBSEQUENTLY SEPARATING AMERICIUM FROM THE SALT MIXTURE.
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公开(公告)号：US3647421A
公开(公告)日：1972-03-07
申请号：US3647421D
申请日：1969-04-04
Applicant: ATOMIC ENERGY COMMISSION
Inventor： NELSON PAUL A , WENZ DONALD A
CPC classification number: C22B60/04
Abstract: Plutonium is recovered from an oxidation-resistant plutonium dioxide-molybdenum fuel by reacting the fuel with molten cupric chloride contained in a molten salt to form a soluble plutonium species, an insoluble molybdenum species and a volatile molybdenum species. Plutonium is reduced and separated from the cupric chloride by mixing the salt with a zinc-magnesium or a cadmium-magnesium alloy which is thereafter retorted to leave essentially pure plutonium metal.
Abstract translation: 通过使燃料与熔融盐中所含的熔融氯化铜反应形成可溶性钚物质，不溶性钼物质和挥发性钼物质，从憎氧氧化钚二氧化钼燃料中回收钚。 钚通过将盐与锌镁或镉镁合金混合而被还原并与氯化铜分离，锌镁或镉镁合金随后被蒸馏以留下基本上纯的钚金属。
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公开(公告)号：US3463634A
公开(公告)日：1969-08-26
申请号：US3463634D
申请日：1968-08-09
Applicant: ATOMIC ENERGY COMMISSION
Inventor： WILHELM HARLEY A , MCCLUSKY JAMES K
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Patent Agency Ranking
公开(公告)号：US3850623A
公开(公告)日：1974-11-26
申请号：US8385361
申请日：1961-01-19
Applicant: ATOMIC ENERGY COMMISSION
Inventor： SHELLER O
CPC classification number: C22B60/0213
Abstract: 1. The method of preparing metallic uranium from UF4 which comprises heating a reaction mixture comprising UF4, calcium in excess of the stoichiometric amount required to reduce said UF4, an ignition agent and Lithium until said mixture ignites, and separating the resulting metal from the resulting slag, said lithium being provided in said mixture in a proportion sufficient to produce a lithium fluoride content of approximately 15 to 30 mole percent in said slag, and said ignition agent being selected from the group consisting of iodine and a finely divided mixture of magnesium with an alkali metal iodate and an alkali metal peroxide.
Abstract translation: 1.从UF4制备金属铀的方法，其包括加热包含UF4，钙超过减少所述UF4所需的化学计量的反应混合物的反应混合物，点燃剂和锂直到所述混合物点燃，并将所得金属与所得的 所述锂在所述混合物中以足以在所述炉渣中产生约15至30摩尔％的氟化锂含量的比例提供在所述混合物中，并且所述点火剂选自碘和镁与镁的微粉碎混合物 碘酸碱金属盐和碱金属过氧化物。
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公开(公告)号：US3677743A
公开(公告)日：1972-07-18
申请号：US3677743D
申请日：1969-06-03
Applicant: ATOMIC ENERGY COMMISSION
Inventor： WALSH WILLIAM J , PIERCE ROBERT DEAN
CPC classification number: G21C19/48 , Y02W30/884
Abstract: A PROCESS AND APPARATUS FOR SEPARATING FISSION PRODUCTS FROM URANIUM AND/OR PLUTONIUM EMPLOYING LIQUID METALS AND LIQUID SALT AS SOLVENT IS DISCLOSED. A SOLUTION OF URANIUM AND/OR PLUTONIUM IN A LIQUID METAL IS FLOWED SEQUENTIALLY INTO AND THROUGH A PLURALITY OF MIXER-SETTLERS CONTAINING A LIQUID SALT WHICH REMOVE CERTAIN FISSION PRODUCTS FROM THE FEED SOLUTION AS WELL AS A SMALL PROPORTION OF THE URANIUM AND/OR PLUTONIUM. THE URANIUM AND/OR PLUTONIUM IS REMOVED FROM THE FEED SOLUTION IN ANOTHER MIXER-SETTLER AND THE LIQUID METAL SOLVENT IS RECYCLED TO THE FIRST MIXER-SETTLER WHERE IT WASHES ALL OF THE URANIUM AND/OR PLUTONIUM FROM THE LIQUID SALT PRESENT THEREIN. THE LIQUID SALT IN THE FIRST MIXER-SETTLER IS DISCARDED, THE LIQUID SALT IN SUBSEQUENT MIZER-SETTLERS IS TRANSFERRED BETWEEN STAGES AND FRESH LIQUID SALT IS ADDED TO THE LAST MIXER-SETTLE. ALSO DISCLOSED IS A SYSTEM INCLUDING A PLURALITY OF MIXER-SETTLERS WHICH INCLUDE AN L-SHAPED BAFFLE IN THE SETTLING CHAMBER.
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公开(公告)号：US3676081A
公开(公告)日：1972-07-11
申请号：US3676081D
申请日：1968-12-31
Applicant: JOSEPH PETER MAZZA
Inventor： MAZZA JOSEPH PETER
CPC classification number: C22B34/1245 , C01F15/00
Abstract: TITANIUM OCCURRING AS AN IMPURITY IN MONAZITE ORES IS REMOVED BY TREATMENT OF A THORIUM CHLORIDE SOLUTION DERIVED FROM SAID ORES WHICH CONTAINS SAID TITANIUM WITH TANNIC ACID TO PRECIPITATE THE TITANIUM, THEREBY REMOVING 90% OR MORE OF THE LATTER.
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公开(公告)号：US3619178A
公开(公告)日：1971-11-09
申请号：US3619178D
申请日：1969-11-14
Applicant: ATOMIC ENERGY COMMISSION
Inventor： FELT ROWLAND E
CPC classification number: C22B60/04
Abstract: Plutonium dioxide is reduced to plutonium metal by adding the plutonium dioxide and calcium to a flux consisting of 5 to 20 weight percent calcium fluoride and 95 to 80 weight percent calcium chloride held at about 800* C. The plutonium dioxide and calcium may be added simultaneously or sequentially; however, the weight of unreacted plutonium dioxide in the flux must never exceed 20 percent of the weight of the flux and no more than a slight excess of calcium may be present in the flux. The plutonium metal is removed to one vessel and the salt removed to another where it is contacted with calcium-30 weight percent zinc to remove residual plutonium therefrom.
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公开(公告)号：US3495954A
公开(公告)日：1970-02-17
申请号：US3495954D
申请日：1967-03-27
Applicant: ATOMIC ENERGY AUTHORITY UK
Inventor： GRIMES JOHN HERBERT , DRESS WILLIAM
IPC: B01J2/02 , B01J2/04 , B01J2/08 , B01J2/20 , B22F3/00 , B22F9/20 , C01B25/26 , C01B31/30 , C01B33/20 , C01F7/34 , C01F15/00 , C01G56/00 , C03C17/25 , C04B41/50 , C22C1/02 , C22C1/10 , C22C32/00 , C22B61/04
CPC classification number: C22C32/00 , B01J2/02 , B01J2/04 , B01J2/08 , B01J2/20 , B22F3/00 , B22F9/20 , C01B25/26 , C01B32/90 , C01B33/20 , C01F7/34 , C01F15/00 , C01G56/004 , C01G56/005 , C01P2004/32 , C01P2006/60 , C01P2006/80 , C03C17/25 , C03C2217/229 , C03C2218/111 , C04B41/5025 , C22C1/02 , C22C1/1026 , C04B41/4505 , C04B41/4584
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