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1. 发明授权

US11817224B2 Equipment for producing nuclear fuel powder 有权
公开(公告)号：US11817224B2
公开(公告)日：2023-11-14
申请号：US17282935
申请日：2018-10-09
申请人： FRAMATOME
发明人： Serge Perrin , Pascal Rouquette
IPC分类号： G21C21/00 , C01G43/025 , B01J12/02 , B01J19/00 , C01B13/22
CPC分类号： G21C21/00 , B01J12/02 , B01J19/00 , C01B13/22 , C01G43/025
摘要： A nuclear fuel powder production plant comprises a conversion installation (2) for the conversion of uranium hexafluoride (UF6) into uranium dioxide (UO2) having a hydrolysis reactor (4) for the conversion of UF6 into uranium oxyfluoride powder (UO2F2) and a pyrohydrolysis furnace (6) for converting the UO2F2 powder into UO2 powder. The nuclear fuel powder production plant also includes a packaging unit (20) for the UO2 powder comprising a filling station (22) having a chamber (26) for receiving a container (24) to be filled, a filling duct (28) supplied from the furnace (6) and a suction system (32) comprising a suction ring (34) disposed at the outlet (30) of the filling duct (28) for sucking an annular air flow (A) around a stream (P) of UO2 powder falling from the outlet (30) from the filling duct (28) into the container (24).

2. 发明授权

US09909229B2 Rubidium uranium fluoride-based crystals and methods of fabrication 有权
公开(公告)号：US09909229B2
公开(公告)日：2018-03-06
申请号：US15077317
申请日：2016-03-22
申请人： The United States of America as Represented by the Secretary of the Air Force
发明人： James M Mann , Eric Hunt
IPC分类号： C30B7/10 , C01B25/45 , C09K11/77 , C30B29/14 , C01G43/025 , C30B7/14 , C30B29/16 , C01G43/00 , C01G43/06 , C30B29/12 , C01B25/455 , C09K11/04
CPC分类号： C30B7/10 , C01B25/45 , C01B25/455 , C01G43/006 , C01G43/025 , C01G43/06 , C01P2002/72 , C01P2002/76 , C01P2002/77 , C01P2006/60 , C09K11/04 , C09K11/7709 , C30B7/14 , C30B29/12 , C30B29/14 , C30B29/16
摘要： A method of synthesizing rubidium uranium fluoride crystals. The method includes combining uranium-based feedstock with a mineralizer solution that includes a rubidium fluoride. The feedstock and mineralizer solution are pressurized and a thermal gradient applied thereto such that a first portion of the feedstock and the mineralizer solution is heated to a temperature that is greater than a temperature of a second portion of the feedstock and the mineralizer solution. Uranium nutrient enters the mineralizer solution from the feedstock in the first portion and uranium nutrient precipitates to spontaneously form crystals in the second portion.

3. 发明申请

US20160272505A1 PROCESS FOR PREPARING A POWDER COMPRISING A SOLID SOLUTION OF URANIUM DIOXIDE AND OF A DIOXIDE OF AT LEAST ONE OTHER ACTINIDE AND/OR LANTHANIDE ELEMENT 有权
标题翻译：制备包含二氧化铀固体溶液的粉末的方法和至少一种其他丙二酸酯和/或兰沙特元素的二氧化物
公开(公告)号：US20160272505A1
公开(公告)日：2016-09-22
申请号：US15031105
申请日：2014-10-22
申请人： COMMISSARIAT À L 'ÉNERGIE ATOMIQUE ET AUX ÉNERGIES ALTERNATIVES , AREVA NC
发明人： Guillaume PETER-SOLDANI , Stephane GRANDJEAN , Francis ABRAHAM
IPC分类号： C01G43/025 , G21C3/62 , C01G56/00
CPC分类号： C01G43/025 , C01G43/00 , C01G56/004 , C01G56/005 , C01G56/007 , C01P2002/50 , G21C3/623 , G21C19/46 , G21C21/02 , Y02E30/38 , Y02W30/883
摘要： The invention relates to a method for preparing a powder of a solid solution of dioxide of uranium and of at least one other actinide and/or lanthanide element comprising a step for combustion of a solution comprising uranyl nitrate and at least one nitrate of the other actinide and/or lanthanide element and nitrogen-containing fuel used according to a specific predetermined amount so as to form at the end of this step, said solid solution.
摘要翻译：本发明涉及一种制备铀二氧化物和至少一种其它锕系元素和/或镧系元素的固溶体的粉末的方法，其包括用于燃烧包含硝酸铀酰和另一种锕系元素的至少一种硝酸盐的溶液的步骤和/或镧系元素和含氮燃料，根据特定的预定量，以在该步骤结束时形成所述固溶体。

4. 发明申请

US20110263837A1 METHOD FOR PREPARING AN ACTINIDE(S) OXALATE AND FOR PREPARING AN ACTINIDE(S) COMPOUND 有权
标题翻译：制备丙交酯（O）和用于制备丙交酯（S）化合物的方法
公开(公告)号：US20110263837A1
公开(公告)日：2011-10-27
申请号：US13139704
申请日：2009-12-17
申请人： Murielle Bertrand , Stephane Grandjean , Bruno Courtaud , Frederic Auger
发明人： Murielle Bertrand , Stephane Grandjean , Bruno Courtaud , Frederic Auger
IPC分类号： C07F5/00
CPC分类号： C01G56/00 , C01G43/025 , C01P2004/03 , C01P2004/51 , G21C3/62 , G21C3/623 , G21C19/46 , Y02E30/38 , Y02W30/883
摘要： A method for preparing an oxalate of one or more actinides for processing and recycling nuclear fuel, comprising: the precipitation of said actinide or the coprecipitation of said actinides in the form of oxalate particles by bringing into contact an aqueous solution containing the actinide(s) with an aqueous solution of oxalic acid or of an oxalic acid salt; and the collection of the resulting oxalate particles; characterized in that the precipitation or coprecipitation is carried out in fluidized bed.
摘要翻译：一种用于制备用于处理和再循环核燃料的一种或多种锕系元素草酸盐的方法，包括：通过与含有锕系元素的水溶液接触，使所述锕系元素沉淀或所述锕系元素以草酸盐颗粒的形式共沉淀，与草酸或草酸盐的水溶液; 并收集所得到的草酸盐颗粒; 其特征在于沉淀或共沉淀在流化床中进行。

5. 发明申请

US20030064519A1 Method and apparatus for determining the progress of a chemical reaction in a furnace and for controlling the reaction 失效
标题翻译：用于确定炉中化学反应进程和控制反应的方法和装置
公开(公告)号：US20030064519A1
公开(公告)日：2003-04-03
申请号：US10203445
申请日：2002-08-08
发明人： Andre Fuegier
IPC分类号： C01G043/01 , G01N033/00
CPC分类号： G21C3/623 , C01G43/025 , C01P2006/80 , G01N33/0036 , Y02E30/38 , Y10T436/12 , Y10T436/153333 , Y10T436/16 , Y10T436/207497
摘要： A substance in a condensed state, for example a powdered solid, is in continuous movement in the longitudinal direction (6) of a furnace (4, 5). A reactive gas mixture is brought into contact with the substance in the condensed state. A plurality of samples of the gaseous mixture are removed at a plurality of reference points (14) spaced apart from one another along the longitudinal direction (6) of the furnace (4, 5); each of the gas samples is analyzed outside the furnace to determine the composition of the gas mixture and for each point (14), the extent of a chemical reaction between the condensed substance and the reactive gas mixture is deduced from the composition of the gas mixture at each of the reference points (14). In particular, the apparatus comprises a sampling and injection rod (10) introduced into the furnace (4, 5) and disposed in its longitudinal direction (6). The invention is of particular application to modeling a rotary furnace (4, 5) for converting uranium oxyfluoride into uranium oxides and for controlling the conversion reaction in the furnace (4, 5).
摘要翻译：处于冷凝状态的物质，例如粉末状固体，在炉（4,5）的纵向（6）上连续运动。使反应性气体混合物与冷凝状态的物质接触。多个样品的气体混合物在沿着炉子4,5的纵向方向（6）彼此间隔开的多个参考点（14）处被去除; 在炉外分析每个气体样品以确定气体混合物的组成，并且对于每个点（14），从气体混合物的组成推导出冷凝物质和反应性气体混合物之间的化学反应的程度在每个参考点（14）处。特别地，该装置包括被引入炉（4,5）中并沿其纵向方向（6）设置的取样和注入杆（10）。本发明特别适用于将用于将铀氧氟化物转化为铀氧化物并用于控制炉子（4,5）中的转化反应的旋转炉（4,5）的建模。

6. 发明申请

US20010014305A1 Method and apparatus for reducing uranium trioxide 有权
标题翻译：减少三氧化铀的方法和装置
公开(公告)号：US20010014305A1
公开(公告)日：2001-08-16
申请号：US09795090
申请日：2001-03-01
发明人： Mikhail Simonovich Ioffe
IPC分类号： C01G043/025
CPC分类号： C01G43/025 , C01P2004/32 , C01P2004/54 , C01P2006/80 , G21C3/623 , Y02E30/38
摘要： Uranium trioxide is reduced to uranium dioxide using microwave radiation or radiofrequency radiation directed in such a way that the radiation encounters an interface between uranium trioxide and the uranium-containing reduction product without first having passed through that product. By this method, and also using a reducing gas, it is possible to obtain UO2 with an O:U ratio less than 2.04:1.
摘要翻译：使用微波辐射或射频辐射将三氧化铀还原成二氧化铀，使得辐射在没有首先通过该产物的情况下遇到三氧化铀和含铀还原产物之间的界面。通过该方法，并且还使用还原气体，可以获得O：U比小于2.04:1的UO2。

7. 发明授权

US6153164A Method for producing uranium oxide from uranium tetrafluoride and a phyllosilicate mineral 有权
标题翻译：从四氟化铀和页硅酸盐矿产生氧化铀的方法
公开(公告)号：US6153164A
公开(公告)日：2000-11-28
申请号：US412061
申请日：1999-10-04
申请人： John B. Bulko , Bridget M. Smyser
发明人： John B. Bulko , Bridget M. Smyser
IPC分类号： C01B9/08 , C01F5/32 , C01F7/60 , C01G43/01 , C01G43/025 , C01B33/10
CPC分类号： C01G43/01 , C01B9/08 , C01F5/32 , C01F7/60 , C01G43/025 , C01P2002/72
摘要： A method for producing uranium oxide includes combining uranium tetrafluoride and a phyllosilicate mineral containing a solid oxidizing agent within the mineral's structure having a lower thermodynamic stability than the uranium oxide; heating the combination below the vapor point of the uranium tetrafluoride to sufficiently react the uranium tetrafluoride and the oxidizing agent to produce uranium oxide and a non-radioactive fluorine compound; and removing the fluorine compound.
摘要翻译：生产氧化铀的方法包括将四氟化铀和含有固体氧化剂的页硅酸盐矿物结合在具有比氧化铀更低的热力学稳定性的矿物结构内; 将低于四氟化铀蒸气点的组合加热以使四氟化铀和氧化剂充分反应生成氧化铀和非放射性氟化合物; 并除去氟化合物。

8. 发明授权

US5935528A Multicomponent fluid feed apparatus with preheater and mixer for a high temperature chemical reactor 失效
标题翻译：具有高温化学反应器预热器和混合器的多组分流体输送装置
公开(公告)号：US5935528A
公开(公告)日：1999-08-10
申请号：US783512
申请日：1997-01-14
申请人： Michael J. Stephenson , Paul A. Haas , David A. Everitt
发明人： Michael J. Stephenson , Paul A. Haas , David A. Everitt
IPC分类号： B01J8/24 , B01J12/02 , B01J19/26 , C01G43/01 , C01G43/025 , C01G43/02
CPC分类号： B01J12/02 , B01J19/26 , B01J8/1827 , C01G43/01 , C01G43/025 , B01J2219/00099 , B01J2219/00119 , B01J2219/00135 , B01J2219/00159
摘要： A multicomponent fluid feed apparatus is disclosed that independently preheats and then mixes two or more fluid streams being introduced into a high temperature chemical reactor to promote more rigorous and complete reactions using assemblies of inert tubular elements and an integral mixing orifice plate. The design allows use of ceramic and speciality alloy materials for high temperature service with particularly corrosive halide feeds such as UF.sub.6 and HF. Radiant heat transfer to the tubular elements from external means gives the necessary system high temperatures without excessive temperatures to cause material failure. Preheating of the gaseous reactants in a separate step prior to mixing and injecting the gaseous reactants into a high temperature chemical reactor was found to provide an improved thermal conversion of UF.sub.6 to uranium oxides.
摘要翻译：公开了一种多组分流体输送装置，其独立地预热然后将引入到高温化学反应器中的两种或更多种流体流混合，以使用惰性管状元件和整体混合孔板的组件来促进更严格和完整的反应。该设计允许使用陶瓷和特种合金材料进行高温维护，特别是腐蚀性卤化物进料如UF6和HF。从外部装置向管状元件的辐射热传递给出必要的系统高温，而没有过多的温度导致材料失效。发现在气态反应物混合并将气态反应物注入高温化学反应器之前，在单独的步骤中预热气态反应物以提供UF 6与氧化铀的改进的热转化。

9. 发明授权

US5918106A Method for producing uranium oxide and a non-radioactive fluorine compound from uranium tetrafluoride and a solid oxide compound 失效
标题翻译：从四氟化铀和固体氧化物化合物制备氧化铀和非放射性氟化合物的方法
公开(公告)号：US5918106A
公开(公告)日：1999-06-29
申请号：US92417
申请日：1998-06-05
申请人： John B. Bulko , William T. Nachtrab
发明人： John B. Bulko , William T. Nachtrab
IPC分类号： C01B9/08 , C01G1/06 , C01G43/01 , C01G43/025 , C01B9/00 , C01B35/06
CPC分类号： C01B9/08 , C01G1/06 , C01G43/01 , C01G43/025 , C01P2002/72
摘要： A method for producing uranium oxide includes combining uranium tetrafluoride and a solid oxidizing agent having a lower thermodynamic stability than the uranium oxide; heating the combination below the vapor point of the uranium tetrafluoride to sufficiently react the uranium tetrafluoride and the oxidizing agent to produce uranium oxide and a non-radioactive fluorine compound; and removing the fluorine compound.
摘要翻译：生产氧化铀的方法包括组合四氟化铀和具有比氧化铀更低的热力学稳定性的固体氧化剂; 将低于四氟化铀蒸气点的组合加热以使四氟化铀和氧化剂充分反应生成氧化铀和非放射性氟化合物; 并除去氟化合物。

10. 发明授权

US5723100A Uranium oxide production 失效
标题翻译：氧化铀生产
公开(公告)号：US5723100A
公开(公告)日：1998-03-03
申请号：US592337
申请日：1996-03-07
申请人： Robert Carter , John Terry Semeraz
发明人： Robert Carter , John Terry Semeraz
IPC分类号： G21C3/62 , C01G43/01 , C01G43/025
CPC分类号： C01G43/025 , C01P2006/12 , C01P2006/80
摘要： A process for the production of a uranium oxide in which UF.sub.6 is converted by reaction with steam into UO.sub.2 F.sub.2 in a first step and by further reaction of UO.sub.2 F.sub.2 with steam and/or hydrogen in a second step to produce an oxide of uranium, the process being carried out in an apparatus comprising a single kiln vessel having a first region, having UF.sub.6 and steam inlets, wherein the fast step may be carried out, and a second region wherein the said second step may be carried out, which process includes the further steps of analysing the oxide of uranium produced to determine the mount of fluoride present and the oxygen to uranium (O/U) ratio therein, and, where the level of fluoride present is unacceptably high, recycling the oxide of uranium to the said second region to produce an oxide of uranium having a lower fluoride content and oxygen to uranium ratio and wherein the said oxide of uranium having the unacceptably high fluoride content is fed into the first region of the vessel, in the absence of any feeding of UF.sub.6 or steam thereto, and conveyed by conveying means directly into the second region of the vessel.
摘要翻译： PCT No.PCT / GB95 / 01281 Sec。 371日期：1995年3月7日 102（e）1995年3月7日PCT PCT。1995年6月2日PCT公布。第WO95 / 33689号公报日期1995年12月14日一种生产氧化铀的方法，其中UF6在第一步骤中通过与蒸汽反应转化成UO2F2而转化，并且在第二步中进一步与UO2F2与蒸汽和/或氢反应以产生氧化铀铀，该方法在包括具有UF 6和蒸汽入口的第一区域的单个窑容器的装置中进行，其中可执行快速步骤，以及可执行所述第二步骤的第二区域，方法包括进一步分析生产的铀氧化物以确定氟化物存在量和其中氧铀（O / U）比率的氧化物，并且当存在的氟化物水平不可接受地高时，将铀氧化物再循环至所述第二区域产生具有较低氟化物含量和氧与铀比率的铀氧化物，并且其中所述具有不可接受的高氟含量的铀氧化物被供给到该第一区域在没有任何进料UF6或蒸汽的情况下，并且由输送装置直接输送到容器的第二区域中。

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