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公开(公告)号：US5582706A
公开(公告)日：1996-12-10
申请号：US458527
申请日：1995-06-02
CPC分类号： C22B60/0213 , C22B60/0295 , C22B60/04 , C25C3/34 , G21C19/48 , Y02W30/884
摘要： A pyrochemical process is utilized to recover 99% of the remaining transuranium materials from plutonium-uranium extraction waste. One step of the overall pyrochemical process involves the electrochemical separation of the waste components. A solid anode and a solid cathode are used in this electrochemical separation step to electrorefine in single or multiple steps. The solid anode and solid cathode are selected from certain preferred anodic and cathodic materials. Where multiple electrorefining steps are used to obtain more complete electroseparation, this is achieved by employing in the multiple electrorefining steps both a solid anode, suitably graphite, and a molten metal anode containing a mixture of the actinide and rare earth elements. This results in greater separation than can be realized through electroseparation by use of either anode alone.
摘要翻译： 利用热化学工艺从铀 - 铀萃取废物中回收99％的剩余的铀钛材料。 整个焦化过程的一个步骤涉及废物组分的电化学分离。 在该电化学分离步骤中使用固体阳极和固体阴极，以单步或多步进行电致精制。 固体阳极和固体阴极选自某些优选的阳极和阴极材料。 当使用多个电解精制步骤来获得更完整的电分离时，这通过在固体阳极，合适的石墨和含有锕系元素和稀土元素的混合物的熔融金属阳极的多个电解精炼步骤中使用来实现。 这导致比通过仅使用任一阳极的电分离可以实现的更大的分离。
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公开(公告)号：US5112534A
公开(公告)日：1992-05-12
申请号：US489296
申请日：1990-03-05
申请人： Jerold Guon , LeRoy F. Grantham , Eugene R. Specht
发明人： Jerold Guon , LeRoy F. Grantham , Eugene R. Specht
IPC分类号： G21C3/60
CPC分类号： G21C3/60 , Y02E30/34 , Y02E30/38 , Y10S376/901
摘要： To increase the operating temperature of a reactor, the melting point and mechanical properties of the fuel must be increased. For an actinide-rich fuel, yttrium, lanthanum and/or rare earth elements can be added, as stabilizers, to uranium and plutonium and/or a mixture of other actinides to raise the melting point of the fuel and improve its mechanical properties. Since only about 1% of the actinide fuel may be yttrium, lanthanum, or a rare earth element, the neutron penalty is low, the reactor core size can be reduced, the fuel can be burned efficiently, reprocessing requirements are reduced, and the nuclear waste disposal volumes reduced. A further advantage occurs when yttrium, lanthanum, and/or other rare earth elements are exposed to radiation in a reactor, they produce only short half life radioisotopes, which reduce nuclear waste disposal problems through much shorter assured-isolation requirements.
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公开(公告)号：US4244693A
公开(公告)日：1981-01-13
申请号：US772627
申请日：1977-02-28
申请人： Jerold Guon
发明人： Jerold Guon
摘要： A method and composition for detecting the presence of an alkali metal on the surface of a body such as a metal plate, tank, pipe or the like is provided. The method comprises contacting the surface with a thin film of a liquid composition comprising a light-colored pigment, an acid-base indicator, and a nonionic wetting agent dispersed in a liquid carrier comprising a minor amount of water and a major amount of an organic solvent selected from the group consisting of the lower aliphatic alcohols, ketones and ethers. Any alkali metal present on the surface in elemental form or as an alkali metal hydroxide or alkali metal carbonate will react with the acid-base indicator to produce a contrasting color change in the thin film, which is readily discernible by visual observation or automatic techniques.
摘要翻译： 提供一种用于检测金属板，罐，管等物体表面上碱金属的存在的方法和组合物。 该方法包括将表面与液体组合物的薄膜接触，所述液体组合物包含浅色颜料，酸碱指示剂和分散在液体载体中的非离子润湿剂，所述液体载体包含少量的水和主要量的有机 溶剂，选自低级脂族醇，酮和醚。 存在于元素表面的碱金属或作为碱金属氢氧化物或碱金属碳酸盐的碱金属将与酸碱指示剂反应，从而通过目视观察或自动技术容易地识别薄膜中的对比色变化。
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公开(公告)号：US5348689A
公开(公告)日：1994-09-20
申请号：US90458
申请日：1993-07-13
申请人： Ricahard L. Gay , Jerold Guon , John C. Newcomb
发明人： Ricahard L. Gay , Jerold Guon , John C. Newcomb
IPC分类号： A62D3/32 , A62D3/38 , A62D101/20 , A62D101/40 , B09B3/00 , C01D7/00 , C01F11/18 , G21F9/06 , G21F9/32 , G21F9/00
CPC分类号： G21F9/32 , C01D7/00 , C01F11/184
摘要： A process for destroying alkali metal and alkaline earth metal-containing wastes, such as sodium, by feeding such waste into a molten bath containing a molten salt such as sodium carbonate, or a mixture of salts having a lower melting point, such as a mixture of sodium carbonate and an alkali metal halide, e.g. sodium chloride, or mixtures of alkali metal chlorides, feeding a mixture of carbon dioxide and oxygen into the molten salt bath and reacting the alkali metal or alkaline earth metal such as sodium in the waste with the carbon dioxide and oxygen to form alkali metal carbonate, e.g. sodium carbonate, in the molten salt bath.
摘要翻译： 通过将这种废物进料到含有熔融盐如碳酸钠的熔融浴或具有较低熔点的混合物如混合物中来破坏含碱金属和碱土金属的废物如钠的方法 的碳酸钠和碱金属卤化物，例如 氯化钠或碱金属氯化物的混合物，将二氧化碳和氧气的混合物进料到熔融盐浴中，并使废弃物中的碱金属或碱土金属如钠与二氧化碳和氧气反应以形成碱金属碳酸盐， 例如 碳酸钠，在熔融盐浴中。
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公开(公告)号：US5390901A
公开(公告)日：1995-02-21
申请号：US126855
申请日：1993-09-27
CPC分类号： A62D3/32 , B01J4/001 , F23G5/444 , A62D2101/06 , A62D2203/10 , F23G2205/125 , F23G2205/14 , F23G2205/16 , F23G2205/18 , Y10S588/90
摘要： A feed system for feeding solid propellant or explosive energetic materials, e.g. in the form of chunks, into a molten salt furnace for destruction of said materials by oxidation with air, while substantially avoiding the danger of detonation of such materials during feeding. The system comprises a feed hopper separated from the molten salt furnace by a barrier such as a concrete wall. The feed hopper is preferably vibrated to move the chunks of waste to an inclined chute which passes through a penetration in the barrier to the furnace, the chute also being preferably vibrated to facilitate passage of the waste material. The chunks of waste are discharged from the inclined chute either directly into the molten salt bath in the furance, or added incrementally thereto by a lock valve arrangement.
摘要翻译： 用于饲养固体推进剂或爆炸能量材料的进料系统，例如 以大块的形式，通过用空气氧化而进入熔盐炉中以破坏所述材料，同时基本避免在进料期间引爆这种材料的危险。 该系统包括通过诸如混凝土壁的障碍物从熔盐炉分离的进料斗。 进料料斗优选地振动以将废物块移动到倾斜的斜槽，该斜槽通过阻挡件中的穿透物进入炉，该滑槽也优选地被振动以促进废料的通过。 大量的废物直接从倾斜的斜槽排出到熔池中，或通过锁阀装置逐渐加入。
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公开(公告)号：US3950152A
公开(公告)日：1976-04-13
申请号：US402937
申请日：1973-10-03
申请人： Jerold Guon
发明人： Jerold Guon
CPC分类号： B01D46/0031 , B01D46/24 , G21C19/30 , B01D2275/206
摘要： A sintered filter trap is adapted for insertion in a gas stream of sodium vapor to condense and deposit sodium thereon. The filter is heated and operated above the melting temperature of sodium, resulting in a more efficient means to remove sodium particulates from the effluent inert gas emanating from the surface of a liquid sodium pool. Preferably the filter leaves are precoated with a natrophobic coating such as tetracosane.
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