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1. 发明授权

US11440809B2 Apparatus and process for thermal denitration, use of such an apparatus and product obtained by means of such a process 有权
公开(公告)号：US11440809B2
公开(公告)日：2022-09-13
申请号：US15735441
申请日：2016-06-10
申请人： Areva NC
发明人： Alex Jourdan , Marc Dupoizat
IPC分类号： B01J8/00 , C01G43/01 , B01J19/24 , B01J19/26 , B01J4/00 , B01D50/20 , B01D39/20 , B01D45/08 , B01D49/00 , B01J6/00
摘要： An apparatus (1) for thermal denitration of a uranyl nitrate hydrate to uranium trioxide UO3. The apparatus (1) comprises a burner (114) and a reaction chamber (110) configured to carry out thermal denitration of uranyl nitrate hydrate and to form uranium trioxide UO3 in the form of particles. The apparatus also comprises a separating chamber (120) suitable for separating UO3 particles from the gases resulting from the thermal denitration carried out in the reaction chamber (110), and at least one filter (130) configured for purifying the gases. The separating chamber (120) is a decanting chamber into which the reaction chamber (110) directly opens out. The filter (130) is capable of performing the separation at a temperature greater than or equal to 350° C. The invention also relates to use of such an apparatus, to a thermal denitration process and to UO3 particles obtained by such a process.

2. 发明授权

US09943874B2 Method and device for generating droplets over a variable spectrum of particle sizes 有权
公开(公告)号：US09943874B2
公开(公告)日：2018-04-17
申请号：US13992605
申请日：2011-11-29
申请人： Méryl Brothier , Dominique Moulinier
发明人： Méryl Brothier , Dominique Moulinier
IPC分类号： B05B17/06 , B22F1/00 , C01G43/00 , C01G43/01 , G21C3/62 , B01J2/04 , B01J2/18
CPC分类号： B05B17/0676 , B01J2/04 , B01J2/18 , B22F1/0096 , C01G43/00 , C01G43/01 , G21C3/62 , G21C3/623 , Y02E30/38
摘要： A process for generating droplets with a modulatable droplet size distribution, comprises: making a stream of liquid strike a support with a given relative impact velocity; making said support vibrate at at least one vibration frequency; heating said support to a impact temperature such that the liquid film formed by the impact and made to vibrate is heated to a principal temperature to form in combination what are called principal droplets from said film; and transporting said droplets via a transfer/braking/sorting system to a liquid for precipitating the principal droplets, said transportation being carried out at a transportation temperature, all of these parameters, namely the relative impact velocity, the vibration frequency, the principal temperature and the transportation temperature allowing the droplet size of said formed principal droplets and the velocity of the latter to be modulated. A device allowing the process to be implemented is also provided.

3. 发明申请

US20160122199A1 Uranium Recovery From UF6 Cylinders 有权
标题翻译：铀回收UF6气瓶
公开(公告)号：US20160122199A1
公开(公告)日：2016-05-05
申请号：US13776785
申请日：2013-02-26
申请人： TRANSPORT LOGISTICS INT'L, INC
发明人： Ronald O. Noe
IPC分类号： C01G43/01
CPC分类号： C01G43/01 , C01G43/00 , C22B60/023 , C23G1/02
摘要： A process for recovering residual uranium from emptied uranium hexafluoride shipping cylinder during cleaning, including rinsing a uranium hexafluoride shipping cylinder with hydrofluoric acid to dissolve a heel of uranium hexafluoride therein to form a mixture of sediment, precipitates and a uranium solution; separating the uranium solution from the sediment and precipitates; mixing sodium hydroxide with the uranium solution to precipitate sodium diuranate; separating the solid sodium diuranate from the sodium fluoride solution formed; re-dissolving the sodium diuranate in sodium carbonate solution to form uranyl carbonate complex solution; and adjusting the pH of uranyl carbonate complex solution further to precipitate uranyl peroxide with the addition of hydrogen peroxide. Sodium fluoride solution produced is further treated to remove fluoride by percolating it through a calcite limestone bed to form calcium fluoride solid.
摘要翻译：包括在清洗过程中从排空的六氟化铀运输工具缸中回收残余铀的过程，包括用氢氟酸冲洗六氟化铀运输工具，以溶解其中的六氟化铀，以形成沉淀物，沉淀物和铀溶液的混合物; 从沉淀物中分离铀溶液并沉淀; 将氢氧化钠与铀溶液混合以沉淀二氢化钠; 从形成的氟化钠溶液中分离固体二异氰酸钠; 将溶解在碳酸钠溶液中的阿魏酸钠再溶解形成碳酸铀酰复合溶液; 并通过添加过氧化氢进一步调节碳酸铀酸酯配位体溶液的pH以进一步沉淀二氧化铀过氧化物。进一步处理生产的氟化钠溶液以通过将其渗透通过方解石石灰石床除去氟化物以形成氟化钙固体。

4. 发明授权

US07803328B2 Microreactor and method of producing the same 失效
标题翻译：微反应器及其制造方法
公开(公告)号：US07803328B2
公开(公告)日：2010-09-28
申请号：US10523070
申请日：2004-02-05
申请人： Hiroshi Yagi , Takeshi Kihara , Koichi Suzuki
发明人： Hiroshi Yagi , Takeshi Kihara , Koichi Suzuki
IPC分类号： B01J19/08 , C01G43/01 , C01B3/02
CPC分类号： C01B3/583 , B01J19/0093 , B01J2219/00783 , B01J2219/00822 , B01J2219/00835 , B01J2219/00873 , C01B3/323 , C01B2203/044 , C01B2203/047 , H01M8/0612 , Y02P70/56 , Y10T29/49982
摘要： A microreactor is configured to have a metal substrate having a microchannel portion on one surface thereof, a heater provided on the other surface of the metal substrate via an insulating film, a catalyst supported on the microchannel portion, and a cover member having a feed material inlet and a gas outlet and joined to the metal substrate so as to cover the microchannel portion. Since the microreactor uses the metal substrate having a high thermal conductivity and a small heat capacity, the efficiency of heat conduction from the heater to the supported catalyst becomes high, and the processing of the metal substrate is easy to facilitate the production.
摘要翻译：微反应器被配置为具有在其一个表面上具有微通道部分的金属基板，经由绝缘膜设置在金属基板的另一表面上的加热器，支撑在微通道部分上的催化剂和具有进料的盖构件入口和气体出口并连接到金属基底以覆盖微通道部分。由于微反应器使用具有高导热性和小热容量的金属基板，因此从加热器到负载型催化剂的热传导效率变高，金属基板的加工容易制造。

5. 发明申请

US20070178036A1 Method of preparing feedstock liquid, method of preparing uranyl nitrate solution, and method of preparing polyvinyl alcohol solution 有权
标题翻译：制备原料液的方法，制备硝酸铀酸盐溶液的方法，以及制备聚乙烯醇溶液的方法
公开(公告)号：US20070178036A1
公开(公告)日：2007-08-02
申请号：US10583906
申请日：2004-12-22
申请人： Masashi Takahashi
发明人： Masashi Takahashi
IPC分类号： C01G43/01
CPC分类号： G21C3/58 , C01G43/00 , G21C21/00 , Y02E30/38
摘要： The object of the present invention is to provide a feedstock liquid, from which fuel kernels with good quality can be produced, and a method of preparing the feedstock liquid. The present invention provides a feedstock liquid with a viscosity from 4.0×10−2 to 6.5×10−2 Pa·s at 15° C., for the production of ammonium diuranate particles. The present invention also provides a method of preparing a feedstock liquid used for the production of ammonium diuranate particles, which includes mixing a uranyl nitrate solution and tetrahydrofurfuryl alcohol to produce a uranyl nitrate mixture, dissolving polyvinyl alcohol in water to produce an aqueous polyvinyl alcohol solution, mixing the aqueous polyvinyl alcohol solution with tetrahydrofurfuryl alcohol to produce a polyvinyl alcohol solution, and mixing the uranyl nitrate mixture with the polyvinyl alcohol solution.
摘要翻译：本发明的目的是提供一种能够生产具有良好质量的燃料颗粒的原料液以及制备原料液体的方法。本发明提供了在15℃下具有4.0×10 -2至6.5×10 -2 Pa粘度的原料液体，用于生产碘化铵颗粒。本发明还提供一种制备用于生产二硫酸铵颗粒的原料液的方法，其包括将硝酸铀酰溶液和四氢糠醇混合以制备硝酸铀酰混合物，将聚乙烯醇溶解在水中以产生聚乙烯醇水溶液将聚乙烯醇水溶液与四氢糠醇混合以制备聚乙烯醇溶液，并将硝酸铀酰混合物与聚乙烯醇溶液混合。

6. 发明授权

US06096281A Method for producing uranium oxide from uranium oxyfluoride 有权
标题翻译：从铀氧氟化物生产铀的方法
公开(公告)号：US06096281A
公开(公告)日：2000-08-01
申请号：US280890
申请日：1999-03-29
申请人： John B. Bulko , Bridget M. Smyser
发明人： John B. Bulko , Bridget M. Smyser
IPC分类号： C01B7/19 , C01B9/08 , C01G43/01 , C01G43/025 , C01G43/06 , C01B9/00 , C01B35/06
CPC分类号： C01G43/01 , C01B7/191 , C01B9/08 , C01G43/025 , C01G43/06 , C01P2002/72 , C01P2006/80
摘要： A method for producing uranium oxide includes combining uranium oxyfluoride and a solid oxidizing agent having a lower thermodynamic stability than the uranium oxide after "oxide"; heating the combination below the vapor point of the uranium oxyfluoride to sufficiently react the uranium oxyfluoride and the oxidizing agent to produce uranium oxide and a non-radioactive fluorine compound; and removing the fluorine compound after "compound".
摘要翻译：生产氧化铀的方法包括在“氧化物”之后组合铀氧氟化物和具有比铀氧化物更低的热力学稳定性的固体氧化剂; 将低于氟氧化铀的蒸气点的组合加热以使氟氧化铀和氧化剂充分反应以产生铀氧化物和非放射性氟化合物; 并在“化合物”之后除去氟化合物。

7. 发明授权

US6033642A Method for producing silicon tetrafluoride from uranium oxyfluoride 有权
标题翻译：从氟氧化铀生产四氟化硅的方法
公开(公告)号：US6033642A
公开(公告)日：2000-03-07
申请号：US280378
申请日：1999-03-29
申请人： John B. Bulko , Bridget M. Smyser
发明人： John B. Bulko , Bridget M. Smyser
IPC分类号： C01B33/107 , C01G43/01 , C01B33/08
CPC分类号： C01B33/10705 , C01G43/01 , C01P2002/72
摘要： A method for producing silicon tetrafluoride includes combining uranium oxyfluoride and silicon dioxide; heating the combination below the melting point of the uranium oxyfluoride to sufficiently react the uranium oxyfluoride and the silicon dioxide to produce non-radioactive silicon tetrafluoride and an oxide of uranium; and removing the silicon tetrafluoride.
摘要翻译：四氟化硅的制造方法包括将铀氧氟化物与二氧化硅结合，将低于氟氧化铀的熔点的组合加热以使氟氧化铀和二氧化硅充分反应以产生非放射性四氟化硅和铀氧化物; 并除去四氟化硅。

8. 发明授权

US5628048A Process for obtaining uranium trioxide by direct thermal denitration of uranyl nitrate 失效
标题翻译：通过硝酸铀酰直接热脱硝获得三氧化铀的方法
公开(公告)号：US5628048A
公开(公告)日：1997-05-06
申请号：US586879
申请日：1996-02-28
申请人： Gilbert Schaal , Robert Faron
发明人： Gilbert Schaal , Robert Faron
IPC分类号： C01B13/34 , C01G43/01
CPC分类号： C01G43/01 , C01P2006/12
摘要： Process for obtaining uranium trioxide from a uranyl nitrate solution, the trioxide obtained having to have a specific surface between 12 and 15 m.sup.2 /g, consisting of producing in a zone of the reaction chamber called the contact zone, a thermomechanical contact between the uranyl nitrate solution, atomized into fine droplets according to a given axis in the contact zone, and a gaseous fluid introduced into the contact zone, the gaseous fluid being at a sufficiently high temperature and having a sufficiently high mechanical energy to carry out, within the contact zone, the dehydration and calcination of the uranyl nitrate.
摘要翻译： PCT No.PCT / FR95 / 00765 Sec。 371日期1996年2月28日 102（e）日期1996年2月28日PCT提交1995年6月12日PCT公布。 WO95 / 34508 PCT出版物日期1995年12月21日从硝酸铀酰溶液中获得三氧化铀的方法，获得的三氧化二氮必须具有12至15m2 / g之间的比表面积，包括在称为接触区的反应室的区域中产生热机械硝酸铀酰溶液之间的接触，根据接触区域中的给定轴线雾化成细微液滴，以及引入接触区域的气态流体，气态流体处于足够高的温度并具有足够高的机械能来进行在接触区内，硝酸铀酰的脱水和煅烧。

9. 发明授权

US4438050A Method for the manufacture of very dense oxidic nuclear fuel bodies 失效
标题翻译：制造非常致密的氧化核燃料体的方法
公开(公告)号：US4438050A
公开(公告)日：1984-03-20
申请号：US190981
申请日：1980-09-26
申请人： Wolfgang Dorr , Gerhard Gradel , Martin Peehs
发明人： Wolfgang Dorr , Gerhard Gradel , Martin Peehs
IPC分类号： G21C3/00 , C01G43/01 , G21C3/62 , G21C21/00
CPC分类号： G21C3/623 , Y02E30/38
摘要： Manufacture of very dense oxidic fuel bodies of UO.sub.2 with rare earth oxides in which pressed blanks are subjected to sintering in an oxidizing atmosphere at relatively low temperature and are sintered in a reducing atmosphere at a higher temperature. This avoids sintering-inhibiting phases and permits very dense bodies with greater content of rare earth oxides to be produced.
摘要翻译：用稀土氧化物制造非常致密的氧化物燃料体，其中压坯在氧化性气氛中在较低温度下进行烧结，并在较高温度下还原气氛中烧结。这避免了烧结抑制阶段，并且允许产生具有更多含量的稀土氧化物的非常致密的体。

10. 发明授权

US4423008A Direct acid elution of anionic exchange resins for recovery of uranium 失效
标题翻译：用于回收铀的阴离子交换树脂的直接酸洗脱
公开(公告)号：US4423008A
公开(公告)日：1983-12-27
申请号：US352288
申请日：1982-02-25
申请人： Tsoung-Yuan Yan
发明人： Tsoung-Yuan Yan
IPC分类号： C22B60/02 , C01G43/01
CPC分类号： C22B60/0265
摘要： A process as disclosed for recovering uranium values from a carbonate leach solution which comprises directly eluting a column of resin onto which uranium has been sorbed by flowing a concentrated acidic eluant through the column without preconditioning and/or post-conditioning the resin. The concentrated acidic eluant may be flowed upward or, preferably, downward through the column.
摘要翻译：公开的用于从碳酸盐浸出溶液中回收铀值的方法，该方法包括通过使浓缩的酸性洗脱液在不预处理和/或后调理的情况下使浓缩的酸性洗脱液流过而直接洗脱出已经吸收了铀的树脂柱。浓缩的酸性洗脱液可以向上流动，或者优选地向下流过柱。

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