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1.发明授权Binder system for the manufacture of nuclear pellets, and the method and product thereof 失效用于制造核粒料的粘合剂体系及其方法和产品
公开(公告)号：US4816187A
公开(公告)日：1989-03-28
申请号：US22032
申请日：1987-03-05
摘要： A fugitive binder composition for compression molding uranium dioxide nuclear fuel comprising the reaction product of a strongly alkali water solution of a diamine and oxalate ions with uranium oxide which is free of carbonates and carbamates, and having the formula:[.sup.+ NH.sub.3 (CH.sub.2).sub.2 NH.sub.3.sup.+ ][UO.sub.2 (C.sub.2 O.sub.4).sub.2 (H.sub.2 O).sub.2 ][.sup.+ NH.sub.3 (CH.sub.2).sub.2 NH.sub.3.sup.+ ].
摘要翻译： 一种用于压缩二氧化铀核燃料的短暂的粘结剂组合物，其包含二胺和草酸根离子的强碱性水溶液与不含碳酸盐和氨基甲酸酯的氧化铀的反应产物，并具有下式：[+ NH 3（CH 2）2 NH 3 + ] [＆upbar＆UO2（C2O4）2（H2O）2] [+ NH3（CH2）2NH3 +]。
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2.发明授权
公开(公告)号：US5066429A
公开(公告)日：1991-11-19
申请号：US596433
申请日：1990-10-12
IPC分类号： C01G43/025 , G21C3/62
CPC分类号： G21C3/623 , C01G43/025 , C01P2004/84 , Y02E30/38
摘要： A process for controlling the oxidation reaction of oxides of uranium and fixing the ratio of oxygen to uranium in uranium oxide compounds by means of a passification process, and the stabilized uranium oxide compounds produced therefrom. The method is especially useful in the production of uranium oxide fuel for nuclear reactors.
摘要翻译： 用于控制铀氧化物的氧化反应并通过过氧化方法固定氧化铀化合物中氧与铀的比例的方法和由其制备的稳定化铀氧化物。 该方法在生产用于核反应堆的铀氧化物燃料方面特别有用。
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3.发明授权Method and binder for the manufacture of nuclear fuel pellets, and the product 失效用于制造核燃料颗粒的方法和粘合剂，以及产品
公开(公告)号：US4696769A
公开(公告)日：1987-09-29
申请号：US744962
申请日：1985-06-17
摘要： A method and binder composition for prolonging the induced plasticity of a particulate ceramic material admixture comprising uranium dioxide and a fugitive binder, and product thereof, for subsequent compaction by compression molding in the manufacture of nuclear fuel pellets. The fugitive binder comprises a reaction product of an amine carbonate or amine carbamate and ammonium oxalate reacted with uranium dioxide at a temperature of at least 65.degree. C. The uranyl oxalate-carbonate reaction product has the composition of (UO.sub.2 (CO.sub.3) (C.sub.2 O.sub.4). 2H.sub.2 O). 2H.sub.2 O.
摘要翻译： 一种用于延长包含二氧化铀和短暂性粘合剂及其制品的颗粒状陶瓷材料混合物的诱导可塑性的方法和粘合剂组合物，用于随后在制造核燃料颗粒中通过压缩成型进行压实。 短暂的粘结剂包括氨基甲酸铵或氨基甲酸胺和氨基酸铵与二氧化铀在至少65℃的温度下反应的反应产物。草酸二烷基酯 - 碳酸酯反应产物的组成为（UO 2（CO 3）（C 2 O 4） 2H 2 O）。 2H2O。
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4.发明授权Binder system for the manufacture of nuclear fuel pellets, and the method and product thereof 失效用于制造核燃料颗粒的粘合剂体系及其方法和产品
公开(公告)号：US4670198A
公开(公告)日：1987-06-02
申请号：US744945
申请日：1985-06-17
IPC分类号： C04B35/51 , C04B35/63 , G21C3/62 , G21C21/02 , G21C21/00 , C01G43/025 , C04B35/64 , C09K11/04
摘要： A reproducible method and stable binder composition for preserving the induced plasticity of a particulate ceramic material admixture comprising uranium dioxide and a fugitive binder, and product thereof, for subsequent compaction by compressing molding in the manufacture of nuclear fuel pellets.
摘要翻译： 一种可重复的方法和稳定的粘合剂组合物，用于保持包含二氧化铀和短暂的粘合剂及其制品的颗粒状陶瓷材料混合物的诱导可塑性，用于随后通过在制造核燃料颗粒中压缩成型而压实。
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5.发明授权Production method for obtaining pressable powder yielding high sinter density pellets without defects 失效获得可产生高烧结密度的颗粒的可压制粉末的生产方法，没有缺陷
公开(公告)号：US5702676A
公开(公告)日：1997-12-30
申请号：US667795
申请日：1996-06-20
IPC分类号： C01G43/025
CPC分类号： C01G43/025 , C01P2006/10 , C01P2006/12
摘要： This invention provides an improved process of preparing UO.sub.2 powder from poor quality, partially oxidized powder containing organic and inorganic impurities. The process is illustrated in the flow chart of FIG. 1 which includes the steps of (a) oxidizing a uranium-containing scrap also containing inorganic and cationic organic impurities; (b) solubilizing, typically with nitric acid, the uranium contained in the oxidized scrap to produce uranyl nitrate; (c) solvent extracting the solubilized product of step (b) to remove cation impurities to provide a purified uranyl nitrate solution; (d) precipitating the purified uranyl nitrate with ammonia to form ammonium diuranate powder; and (e) calcining and passivating the ammonium diuranate powder to produce UO.sub.2 powder; and optionally (f) forming the UO.sub.2 powder of step (e) into pellets and sintering the formed pellets to produce sintered UO.sub.2 pellets.
摘要翻译： 本发明提供了一种由劣质的部分氧化粉末制备含有机和无机杂质的氧化铝粉末的改进方法。 该过程在图5的流程图中示出。 1，其包括以下步骤：（a）氧化含有无机和阳离子有机杂质的含铀废料; （b）通常用硝酸溶解氧化废料中所含的铀以产生硝酸铀酰; （c）溶剂萃取步骤（b）的溶解产物以除去阳离子杂质以提供纯化的硝酸铀酰溶液; （d）用氨沉淀净化的铀酰硝酸铀以形成十二烷酸铵粉末; 和（e）煅烧和钝化二异氰酸铵粉末以产生UO2粉末; 和（f）将步骤（e）的UO 2粉末形成颗粒并烧结所形成的颗粒以制备烧结的UO2颗粒。
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公开(公告)号：US5613186A
公开(公告)日：1997-03-18
申请号：US584547
申请日：1996-01-11
CPC分类号： G21C19/46 , C01G99/006 , C22B60/026 , G01N2030/143 , G01N2030/8809 , Y02W30/883
摘要： Technetium-99 is quantitatively determined in samples containing uranium using extraction chromatography to remove uranium which otherwise interferes in detecting technetium-99 in low concentrations.
摘要翻译： 锝-99在含铀样品中使用提取色谱定量测定，以除去铀，否则会干扰低浓度检测锝-99。
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7.发明授权
公开(公告)号：US4168914A
公开(公告)日：1979-09-25
申请号：US803727
申请日：1977-06-06
CPC分类号： B01J8/1818 , B01F13/0294 , Y10S423/16
摘要： A mixture of fine and cohesive powders is blended to complete homogeneity in a nuclear-safe bubbling-bed fluidized bed blender having an improved fluidizing grid. The blender includes a generally vertically-oriented slab-shaped, nuclear-safe mixing vessel having a fluidizing grid disposed at one end of the vessel. The fluidizing grid comprises a linear array of generally downwardly-directed, pyramidal-shaped hoppers each having walls converging into a conically-shaped opening. A plurality of ball valves are employed, one such valve being disposed at the bottom of each hopper. The rotary closure member of each of the ball valves includes a first set of gas orifices for directing a flow of fluidizing gas upwardly in a divergent swirl-shaped pattern along the walls of each of the hoppers. In one embodiment a second set of fluidizing gas orifices for directing a flow of fluidizing gas downwardly into the apex of each of the hoppers is also provided. During blending, fluidizing gas is supplied to the first set of orifices, or to a combination of the first and second sets of orifices, in an amount sufficient to cause bubbles of fluidizing gas to rise through the mixture of powders and emerge from the top surface of the powders until a homogeneous blend of powders is achieved.
摘要翻译： 混合精细和粘性粉末的混合物以在具有改进的流化网格的核安全鼓泡床流化床混合器中完成均匀性。 该混合器包括一个大致垂直取向的板状的核安全混合容器，其具有设置在容器一端的流化栅格。 流化栅格包括大致向下定向的金字塔形的料斗的线性阵列，每个具有会聚到锥形开口的壁。 使用多个球阀，一个这样的阀设置在每个料斗的底部。 每个球阀的旋转关闭构件包括第一组气体孔，用于沿着每个料斗的壁沿着发散的漩涡形图案向上引导流化气体流。 在一个实施例中，还提供了用于将流化气体向下引导到每个料斗的顶点的第二组流化气体孔。 在混合期间，将流化气体以足以使流化气体的气泡上升通过粉末混合物并从顶表面出来的量将第一组孔口或第一组孔口的组合供应到第一组孔口 的粉末，直到达到均匀的粉末混合物。
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公开(公告)号：US5473648A
公开(公告)日：1995-12-05
申请号：US228776
申请日：1994-04-18
CPC分类号： C22B34/14 , G21Y2004/60
摘要： The present invention relates to a process of decontaminating zirconium-based alloy claddings tubes used in nuclear reactor fuel rods. The process involved the use of a permanganate in a dilute acid solution. The process renders the alloy suitable for uncontrolled release into a non-radioactive environment.
摘要翻译： 本发明涉及在核反应堆燃料棒中使用的锆基合金包层管的净化方法。 该方法涉及在稀酸溶液中使用高锰酸盐。 该方法使合金适合不受控制地释放到非放射性环境中。
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公开(公告)号：US5069888A
公开(公告)日：1991-12-03
申请号：US387187
申请日：1989-07-31
申请人： Richard I. Larson , Abdul G. Dada , John L. Harmon
发明人： Richard I. Larson , Abdul G. Dada , John L. Harmon
CPC分类号： C04B41/009 , C01G43/025 , C04B41/4584 , C04B41/81 , G21C3/62 , C01P2002/20 , C01P2002/78 , C01P2004/84 , C01P2006/10 , C01P2006/12 , C01P2006/60 , C01P2006/80 , C01P2006/82 , Y02E30/38
摘要： A method of passivating the surface of particulate uranium oxides is disclosed comprising a process of continuously contacting uranium oxide particles with an oxygen containing and cooling counter flowing gas stream. The treatment produces a protective surface which inhibits subsequent oxygen chemisorption of the particulate uranium oxides.
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10.发明授权
公开(公告)号：US5401664A
公开(公告)日：1995-03-28
申请号：US74644
申请日：1993-06-10
CPC分类号： G01N31/00 , G01N30/7206 , Y10T436/10 , Y10T436/109163 , Y10T436/13 , Y10T436/16 , Y10T436/163333 , Y10T436/24 , Y10T436/25 , Y10T436/25375
摘要： A safe analytical technique for determining the concentration amount of dibutyl and monobutyl phosphate degradation products in the TBP-dodecane solvent used in solvent extraction processes. This method of chemical analysis eliminates the use of diazomethane, which is toxic and explosive, thereby providing a safer laboratory technique for routine analyses required to monitor production solvent extraction processes. The solvent sample to be analyzed is spiked with mass labelled, deuterated dibutyl and monobutyl phosphates, which act as internal standards. After adding a silylating agent, bistrimethylsilyltrifluoracetamide, the sample is injected into a gas chromatograph/mass spectrometer, which measures the ratio between the labelled internal standard and the naturally occurring material to obtain a quantitative result.
摘要翻译： 一种用于确定溶剂萃取过程中使用的TBP-十二烷溶剂中二丁基和一丁基磷酸酯降解产物浓度的安全分析技术。 这种化学分析方法消除了使用有毒和爆炸性的重氮甲烷，从而为监测生产溶剂萃取过程所需的常规分析提供了更安全的实验室技术。 待分析的溶剂样品加上标有质量标记的氘代二丁基和单丁基磷酸酯，其作为内部标准。 加入甲硅烷基化剂双三甲基甲硅烷基三氟乙酰胺后，将样品注入气相色谱/质谱仪中，测量标记内标与天然物质的比例，得到定量结果。
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