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公开(公告)号：US4235740A
公开(公告)日：1980-11-25
申请号：US20012
申请日：1979-03-13
CPC分类号： G21C3/623 , C01G56/003 , C01G56/004 , C01P2004/61 , C01P2006/10 , C01P2006/11 , C01P2006/12 , C01P2006/20 , C01P2006/80 , Y02E30/38 , Y10S376/901
摘要： Manufacture of uranium/plutonium oxide mixed crystals soluble in nitric acid in which a solution of uranium nitrate and plutonium nitrate are oxidized to cause the plutonium to reach valence VI. The oxidized solution is admixed with ammonium carbonate, oxalate or carbamate and the pH adjusted to 8.1 to 8.5 to precipitate an ammonium uranyl plutonyl carbonate, oxalate or carbamate. The precipitate is calcined to uranium/plutonium oxide.
摘要翻译： 制造可溶于硝酸的铀/钚氧化物混合晶体，其中硝酸铀和硝酸钚的溶液被氧化，导致钚达到VI。 将氧化的溶液与碳酸铵，草酸盐或氨基甲酸铵混合，并将pH调节至8.1至8.5，以沉淀碳酸铀酰基脯氨酸碳酸酯，草酸盐或氨基甲酸铵。 将沉淀物煅烧成铀/钚氧化物。
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公开(公告)号：US4565672A
公开(公告)日：1986-01-21
申请号：US556638
申请日：1983-11-30
IPC分类号： C01G56/00
CPC分类号： C01G56/005 , C01G56/003 , C01P2006/80
摘要： A method for manufacturing Pu.sub.2 -containing crystals by oxidizing plutonium in a heavily contaminated nitric acid starting solution to Pu.sup.6+, precipitating ammonium plutonyl carbonate containing crystals by reaction with ammonium- and carbonate ions and subsequent separating and calcining of these crystals. The nitric acid solution with the oxidized Pu.sup.6+ as well as carbonate and/or acetate ions and NH.sub.3 are dosed into an aqueous starting solution of ammonium carbonate or ammonium acetate in a concentration such that the mol ratio of carbonate and/or acetate ions to the Pu.sup.6+ -ions in the solution is at least 4:1 and plutonium containing carbonato- or acetato complex compounds which remain dissolved in the receiver solution, are formed, while difficult-to-dissolve metal hydroxide compounds are precipitated. Thereupon NH.sub.3 and carbonate ions are added to precipitate the ammonium plutonyl carbonate containing crystals.
摘要翻译： 通过将重度污染的硝酸起始溶液中的钚氧化成Pu6 +，通过与铵和碳酸根离子反应沉淀出含有结晶的铵基磷酸酯，随后分离和煅烧这些晶体，从而制造含Pu2的晶体的方法。 将具有氧化的Pu6 +以及碳酸盐和/或乙酸根离子和NH 3的硝酸溶液配制成碳酸铵或乙酸铵的起始水溶液，其浓度使得碳酸盐和/或乙酸根离子与Pu6 + 形成溶液中至少4:1，并且难以溶解的金属氢氧化物化合物沉淀而形成保留溶解在接收溶液中的钚的碳酸或乙酸络合物化合物。 因此，加入NH 3和碳酸根离子以沉淀含有含磷酸onyl基碳酸酯的晶体。
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公开(公告)号：US4923639A
公开(公告)日：1990-05-08
申请号：US339753
申请日：1982-01-15
申请人： Wolfgang Stoll , Christian Ost , Volker Schneider
发明人： Wolfgang Stoll , Christian Ost , Volker Schneider
CPC分类号： C01G56/004 , C01G43/00 , C01G43/006 , C01G56/003
摘要： Method for treating plutonium and/or uranyl nitrate by superheating and concentrating a nitric acid starting solution, characterized by the feature that nitric acid starting solution is concentrated to form a Pu(VI)-and/or U(VI)-containing nitrate melt, is poured into a mold, is solidified by cooling down, and is transported and/or stored as a solidified solid body until further processing.
摘要翻译： 通过过硝酸浓缩硝酸起始溶液处理钚和/或硝酸铀酰的方法，其特征在于将硝酸起始溶液浓缩形成含有（Ⅵ）和/或U（Ⅵ）的硝酸盐熔体， 倒入模具中，通过冷却固化，并作为固化固体运送和/或储存直到进一步加工。
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公开(公告)号：US4528130A
公开(公告)日：1985-07-09
申请号：US311072
申请日：1981-10-13
CPC分类号： C01F15/00 , C01G56/004 , G21C19/46 , Y02W30/883
摘要： Method for dissolving hard-to-dissolve thorium and/or plutonium oxides, especially dioxides such as ThO.sub.2, PuO.sub.2 or (U/Pu)O.sub.2 mixed oxides by heating the oxides in a hermetically sealed vessel in fluoride-free nitric acid. The use of a gas atmosphere containing oxygen in the sealed vessel is advantageous.
摘要翻译： 通过在不含氟的硝酸中的密封容器中加热氧化物，溶解难溶解的钍和/或钚氧化物，特别是二氧化物如ThO 2，PuO 2或（U / Pu）O 2混合氧化物的方法。 在密封容器中使用含氧的气体气氛是有利的。
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公开(公告)号：US4514364A
公开(公告)日：1985-04-30
申请号：US518142
申请日：1983-07-28
申请人： Wolfgang Stoll , Karl Ennerst
发明人： Wolfgang Stoll , Karl Ennerst
CPC分类号： G21C19/34 , Y02W30/881
摘要： Reprocessing a nuclear reactor fuel rod which contains nuclear fuel in a cladding tube, by removing the cladding tube from the nuclear fuel. The cladding tube is uniformly heated in hermetically sealed condition together with the nuclear fuel contained thereon to permanently expand the diameter of the cladding tube without the formation of cracks in the cladding tube, increasing the distance between the nuclear fuel and the cladding tube. Subsequently the expanded cladding tube is opened at one end. The nuclear fuel is removed from the opened cladding tube and is processed further, separate from the cladding tube.
摘要翻译： 通过从核燃料中除去包层管，在包壳管中重新加工含有核燃料的核反应堆燃料棒。 包壳管与其中所含的核燃料一起在密封状态下被均匀地加热，以永久地扩大包层管的直径，而不会在包壳管中形成裂纹，从而增加核燃料和包层管之间的距离。 随后，扩展包层管在一端打开。 核燃料从开放的包层管中除去，并与包层管分离。
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公开(公告)号：US4672213A
公开(公告)日：1987-06-09
申请号：US675515
申请日：1984-11-28
申请人： Wolfgang Stoll , Ralf Guldner
发明人： Wolfgang Stoll , Ralf Guldner
CPC分类号： G21F5/005
摘要： Container, especially for radioactive substances such as radioactive liquids, with an inner container for receiving these substances and an outer container, in which the inner container and thermal insulation between the inner and outer container are located. The inner container is associated with a cooling tube within the outer container which tube contains a coolant that can be circulated. A heat discharge tube likewise containing the coolant that can be circulated is arranged at the outer container. The cooling tube and the heat discharge tube are in communication with each other via connecting lines at both tube ends.
摘要翻译： 集装箱，特别是用于放射性物质的放射性物质，具有用于容纳这些物质的内部容器和外部容器，内部容器和内部和外部容器之间的隔热件位于其中。 内部容器与外部容器内的冷却管相关联，该管包含可循环的冷却剂。 同样容纳能够循环的冷却剂的散热管布置在外部容器中。 冷却管和放热管通过两端的连接线彼此连通。
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公开(公告)号：US4434137A
公开(公告)日：1984-02-28
申请号：US212453
申请日：1980-12-03
申请人： Wolfgang Stoll , Wilhelm Ledebrink
发明人： Wolfgang Stoll , Wilhelm Ledebrink
CPC分类号： G21C19/46 , Y02W30/883
摘要： Dissolving hard-to-dissolve nuclear fuels such as ThO.sub.2 and PuO.sub.2 in a nitric acid fission material solution which contains nitric acid and a Pu-fluoride complex to provide free fluorine ions in a small catalytically active amount due to small dissociation of fluoride ions from the Pu-fluoride complex. This permits dissolving hard-to-dissolve nuclear fuels in normal metallic dissolving vessels and also eliminates need for using polytetrafluoroethylene.
摘要翻译： 在含有硝酸和Pu-氟化物络合物的硝酸裂变材料溶液中溶解难溶解的核燃料如ThO 2和PuO 2，以提供小的催化活性量的游离氟离子，这是由于氟离子从 普氟化合物。 这允许在正常的金属溶解容器中溶解难溶解的核燃料，并且也消除了使用聚四氟乙烯的需要。
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公开(公告)号：US4293438A
公开(公告)日：1981-10-06
申请号：US116933
申请日：1980-01-30
摘要： Recovering fission material from solid raw wastes and producing a space-saving product which can be committed to ultimate storage by the following steps:(a) a comminution of the raw wastes to a grain size of about 5 mm(b) dissolution thereof at elevated temperature in an organic solvent until a concentration of about 10 percent by weight is reached(c) separation of insoluble raw waste particles larger than 1 mm.(d) separation of the undissolved fission material content remaining in the polymer solution by means of a centrifuge(e) evaporation and condensation of the solvents for return into the dissolving process according to (b)(f) embedding the waste component from (c) into the remaining plastic melt(g) drawing-off the melt and solidification thereof in storage containers.
摘要翻译： 从固体废物中回收裂变材料，并生产节省空间的产品，可以通过以下步骤致力于最终储存：（a）将生物废物粉碎至约5mm的粒度（b）在高架 在有机溶剂中的温度直到达到约10重量％的浓度（c）分离大于1mm的不溶性废弃废物颗粒。
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