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31. 发明授权

US07608209B2 Use of sintered mixed carbonates for the confinement of radioactive carbon 失效
标题翻译：烧结混合碳酸盐用于限制放射性碳的使用
公开(公告)号：US07608209B2
公开(公告)日：2009-10-27
申请号：US10543448
申请日：2004-10-21
申请人： Agnès Grandjean , Gilles Leturcq , Christophe Baron
发明人： Agnès Grandjean , Gilles Leturcq , Christophe Baron
IPC分类号： C01F17/00 , C01B31/24 , G21F9/16 , G21C21/00
CPC分类号： G21F9/28 , G21F9/02 , G21F9/301
摘要： The present invention relates to the use of a mixed carbonate of formula AB(CO3)2, in which A and B are different and chosen from alkali metals, alkaline-earth metals and rare earths, for the containment of radioactive carbon. This use may for example involve a process comprising: mixing CO2 having a radioactive carbon to be contained, or a simple carbonate of an alkali, alkaline-earth or rare-earth metal having a radioactive carbon to be contained, with an aqueous solution of a mixture of ACln and BClm or with an aqueous solution of a mixture of A(OH)n, and B(OH)m in order to obtain a precipitate of AB(CO3)2, where n and m are integers sufficient to compensate for the charge of A and B respectively; recovery of the AB(CO3)2 precipitate in powder form; and then pressing and sintering of the powder at a 20 temperature below the decarbonation temperature of the mixed carbonate manufactured in order to obtain sintered pellets of mixed carbonates for the containment of the radioactive carbon.
摘要翻译：本发明涉及式AB（CO3）2的混合碳酸酯的用途，其中A和B不同，并选自碱金属，碱土金属和稀土，用于容纳放射性碳。该用途可以例如涉及一种方法，其包括：将要包含的放射性碳的CO 2或具有待包含的放射性碳的碱金属，碱土金属或稀土金属的简单碳酸盐与具有放射性碳的水溶液 ACln和BClm的混合物或与A（OH）n和B（OH）m的混合物的水溶液以获得AB（CO 3）2的沉淀物，其中n和m是足以补偿分别收费A和B; 以粉末形式回收AB（CO3）2沉淀物; 然后在低于制造的混合碳酸盐的脱碳温度的20℃下压制和烧结粉末，以获得用于容纳放射性碳的混合碳酸酯的烧结颗粒。

32. 发明授权

US07349804B2 Daytime stellar imager 有权
公开(公告)号：US07349804B2
公开(公告)日：2008-03-25
申请号：US11141526
申请日：2005-05-31
申请人： Mikhail Belenkii , Donald G. Bruns , Vincent A Rye , Timothy Brinkley
发明人： Mikhail Belenkii , Donald G. Bruns , Vincent A Rye , Timothy Brinkley
IPC分类号： G21C21/00
CPC分类号： G01C21/025
摘要： An automatic celestial navigation system for navigating both night and day by observation of K-band or H-band infrared light from multiple stars. In a first set of preferred embodiments three relatively large aperture telescopes are rigidly mounted on a movable platform such as a ship or airplane with each telescope being directed at a substantially different portion of sky. Embodiments in this first set tend to be relatively large and heavy, such as about one cubic meter and about 60 pounds. In a second set of preferred embodiments one or more smaller aperture telescopes are pivotably mounted on a movable platform such as a ship, airplane or missile so that the telescope or telescopes can be pivoted to point toward specific regions of the sky. Embodiments of this second set are mechanically more complicated than those of the first set, but are much smaller and lighter and are especially useful for guidance of aircraft and missiles. Telescope optics focus (on to a pixel array of a sensor) H-band or K-band light from one or more stars in the field of view of each telescope. Each system also includes an inclinometer, an accurate timing device and a computer processor having access to catalogued infrared star charts. The processor for each system is programmed with special algorithms to use image data from the infrared sensors, inclination information from the inclinometer, time information from the timing device and the catalogued star charts information to determine positions of the platform. Direction information from two stars is needed for locating the platform with respect to the celestial sphere. The computer is also preferably programmed to use this celestial position information to calculate latitude and longitude which may be displayed on a display device such as a monitor or used by a guidance control system. These embodiments are jam proof and insensitive to radio frequency interference. These systems provide efficient alternatives to GPS when GPS is unavailable and can be used for periodic augmentation of inertial navigation systems.

33. 发明申请

US20050220260A1 Method of surface-treating reactor member and method of manufacturing reactor member by using the surface treatment method 失效
标题翻译：表面处理反应器构件的方法和使用表面处理方法制造反应器构件的方法
公开(公告)号：US20050220260A1
公开(公告)日：2005-10-06
申请号：US11041305
申请日：2005-01-25
申请人： Kazuki Monaka , Juntaro Shimizu , Yoichiro Yamaguchi
发明人： Kazuki Monaka , Juntaro Shimizu , Yoichiro Yamaguchi
IPC分类号： G21C21/00 , G21C3/07 , G21C3/12 , G21C3/33 , G21C15/00
CPC分类号： G21C3/07 , G21C3/12 , G21Y2002/103 , G21Y2004/201 , G21Y2004/202 , Y02E30/40 , Y10S148/908 , Y10S376/90
摘要： A method of surface-treating a reactor member for effectively removing a Cr-deficient layer and a work-hardened layer considered to be a cause of stress corrosion cracking (SCC) under low-stress conditions. The method of surface-treating a reactor member which is worked by bending (step 1) and then processed by a heat treatment (step 2), in which a work-hardened layer is formed by the bending, and in which a Cr-deficient layer is formed due to an oxide film attached by the heat treatment, uses at least one of: acid wash; grinding; electrolytic polishing; electro-discharge machining; surface cutting; surface deoxidation and softening; wet blasting; laser machining; or surface plating (step 3) to remove the work-hardened layer and the Cr-deficient layer from the reactor member or to prevent contact of the work-hardened layer and the Cr-deficient layer of the reactor member with a primary coolant.
摘要翻译：在低应力条件下，有效地除去被认为是应力腐蚀开裂原因（SCC）的Cr缺陷层和加固硬化层的反应器构件的表面处理方法。表面处理通过弯曲（步骤1）进行加工，然后通过热处理（步骤2）进行加工的反应器构件的表面处理方法，其中通过弯曲形成加工硬化层，并且其中Cr缺陷由于通过热处理而附着的氧化膜形成层，使用以下中的至少一种：酸洗; 研磨电解抛光; 放电加工; 表面切割; 表面脱氧和软化; 湿喷激光加工; 或表面电镀（步骤3）以从反应器构件去除加固硬化层和Cr缺陷层，或者防止加固硬化层和反应器构件的Cr缺陷层与初级冷却剂接触。

34. 发明授权

US06931090B2 Method of establishing a nuclear reactor core fuel assembly loading pattern 有权
标题翻译：建立核反应堆堆芯燃料装配模式的方法
公开(公告)号：US06931090B2
公开(公告)日：2005-08-16
申请号：US10374691
申请日：2003-02-25
申请人： Yung-An Chao , Shengyi Si , Frank D. Popa
发明人： Yung-An Chao , Shengyi Si , Frank D. Popa
IPC分类号： G21C21/00 , G21C5/00 , G21C5/02 , G21C7/00 , G21C17/00 , G21C19/20 , G21C19/00
CPC分类号： G21C5/00 , G21C5/02 , G21C7/00 , G21C19/205 , G21D3/001 , G21D2003/002 , G21Y2002/201 , G21Y2002/304 , G21Y2004/40 , G21Y2004/403 , Y02E30/39
摘要： All possible loading patterns for a nuclear reactor core are searched and optimized for compliance with design constraints. The fuel inventory is divided into a few batches according to coarse levels of reactivity. A recursive enumeration process identifies patterns meeting selected core position constraints, which can be user modified to adjust the search space size. For the batch loading patterns satisfying the constraints, the batches are divided into several smaller batches. A sensitivity matrix linearizing the relationship between fuel assembly position and the depletion model is processed through mixed integer linear programming with branching and bounding to identify an optimal daughter loading pattern. The process is repeated through several levels of batch refinement and selection of optimal daughter patterns, including a level where burnable absorbers are assigned to feed assemblies, until the individual fuel assembly level is reached. The multiple optimal patterns remaining provide a range of solutions.
摘要翻译：搜索和优化核反应堆核心的所有可能的加载模式，以符合设计约束。燃料库存根据粗略的反应性分为几批。递归计数过程确定满足选定核心位置约束的模式，可以通过用户修改来调整搜索空间大小。对于满足约束的批量加载模式，批次分为几个较小的批次。通过具有分支和边界的混合整数线性规划来处理线性化燃料组装位置和耗尽模型之间的关系的灵敏度矩阵，以识别最佳的子载荷模式。该过程通过几个级别的批次精炼和最佳子模式的选择重复，包括将可燃吸收器分配给进料组件的水平，直到达到单独的燃料组件水平。剩余的多种最佳模式提供了一系列解决方案。

35. 发明申请

US20050167861A1 Mox fuel fabrication process from weapon plutonium feed 有权
标题翻译：来自武器钚饲料的Mox燃料制造工艺
公开(公告)号：US20050167861A1
公开(公告)日：2005-08-04
申请号：US10505428
申请日：2002-03-11
申请人： Alain Vandergheynst , Eduard Pelckmans , Marc De Vleeschauwer
发明人： Alain Vandergheynst , Eduard Pelckmans , Marc De Vleeschauwer
IPC分类号： G21C3/62 , G21C21/00
CPC分类号： G21C3/623 , G21Y2002/601 , G21Y2004/60 , Y02E30/38
摘要： Process for fabrication MOX fuel from weapon originating plutonium oxide (W—PuO2), including a process for fabricating MOX fuel pellets, a dry processing of W—PuO2 powder, and a dry processing of MOX fabrication scrap.
摘要翻译：制造来自武器源钚氧化物（W-PuO 2）的MOX燃料的方法，包括制造MOX燃料颗粒的方法，W-PuO 2粉末的干法处理，和MOX制造废料的干法处理。

36. 发明申请

US20050153007A1 Apparatus and method for fabricating high purity, high density metal matrix composite materials and the product thereof 审中-公开
标题翻译：制造高纯度，高密度金属基复合材料及其制品的装置及方法
公开(公告)号：US20050153007A1
公开(公告)日：2005-07-14
申请号：US10961952
申请日：2004-10-08
申请人： Robin Carden
发明人： Robin Carden
IPC分类号： B22F3/03 , G21C21/00 , B22D17/00
CPC分类号： G21C21/00 , B22F3/03 , B22F2998/00 , B22F2998/10 , B22F2999/00 , B22F3/12 , C22C1/10 , C22C32/00 , C22C1/05 , B22F3/02 , B22F3/10 , B22F2201/20
摘要： A method of production of large Ingots of neutron attenuating composites using a vacuum-bellows system allows for large cross-sectional shapes to be extruded and rolled. A vacuum-bellows technology which allows the manufacturing of large diameter ingots. A variety of primary metal matrix materials can be used in this technology. High specific strength and stiffness can be achieved because the technology allows for final densities of 99% and higher. The vacuum-bellows technology allows metals and ceramics to blend and mesh together at compression pressures of 800 tons with elevated temperatures. The controlled compression movement allows for any oxide layer, on the metal, to be broken up and consolidated with the chosen ceramic particulate. By controlling the amount of boron-rich ceramics, by volume or weight, certain B-10 isotope areal densities can be accomplished. These B-10 isotopes attenuate neutrons in nuclear fuel. Other elements, which have high, cross-sectional Barn values can be used.
摘要翻译：使用真空波纹管系统生产大型中子衰减复合材料的方法允许挤出和轧制大的横截面形状。真空波纹管技术，允许制造大直径的锭。在这种技术中可以使用各种主要金属基质材料。可以实现高比强度和刚度，因为该技术允许最终密度为99％以上。真空波纹管技术允许金属和陶瓷在800吨压缩压力下与高温混合并啮合在一起。受控的压缩运动允许在金属上的任何氧化物层被分解并与选定的陶瓷颗粒固结。通过根据体积或重量控制富含硼的陶瓷的量，可以实现某些B-10同位素面密度。这些B-10同位素减弱了核燃料中的中子。可以使用具有高横截面谷值的其他元件。

37. 发明授权

US06909766B2 Production method for a nuclear fuel assembly support grid and a nuclear fuel assembly support grid produced by the same 失效
标题翻译：核燃料组件支撑网格和由其生产的核燃料组件支撑网格的生产方法
公开(公告)号：US06909766B2
公开(公告)日：2005-06-21
申请号：US10287505
申请日：2002-11-05
申请人： Toshiya Kido , Kimio Nakayama , Yasunao Yamaguchi
发明人： Toshiya Kido , Kimio Nakayama , Yasunao Yamaguchi
IPC分类号： G21C3/34 , C21D1/26 , C22F1/00 , C22F1/18 , G21C3/32 , G21C21/00
CPC分类号： G21C21/00 , G21C3/3206 , G21Y2002/103 , G21Y2002/206 , G21Y2002/303 , G21Y2004/201 , G21Y2004/40 , Y02E30/40
摘要： One object of the present invention is to provide a production method for a nuclear fuel assembly support grid that improves the corrosion resistance of welded parts without impairing the characteristics of the support grid so as to be able adequately withstand highly efficient operation. In order to achieve the object, the present invention provide a production method for a nuclear fuel assembly support grid comprising the steps of: assembling a plurality of straps in a grid form; welding intersections of each strap; and carrying out annealing thereafter to precipitate an intermetallic compound on the welded parts.
摘要翻译：本发明的一个目的是提供一种用于提高焊接部件的耐腐蚀性的核燃料组件支撑格栅的制造方法，而不会损害支撑格栅的特性，从而能够充分地承受高效率的操作。为了实现该目的，本发明提供了一种用于核燃料组件支撑格栅的制造方法，包括以下步骤：以网格形式组装多个带; 每个胶带的焊接交叉点; 然后进行退火以在焊接部分上沉淀金属间化合物。

38. 发明授权

US06878313B2 Method of fabricating sintered nuclear fuel compact 失效
标题翻译：制造烧结核燃料压块的方法
公开(公告)号：US06878313B2
公开(公告)日：2005-04-12
申请号：US10219724
申请日：2002-08-15
申请人： Shin-ichi Kobayashi , Katsuo Fukumoto
发明人： Shin-ichi Kobayashi , Katsuo Fukumoto
IPC分类号： G06F9/44 , G21C3/62 , G21C21/00 , C04B33/32
CPC分类号： G21C21/00 , G21C3/623 , Y02E30/38
摘要： To furnish stably a sintered nuclear fuel compact of uranium dioxide with a large grain diameter, a fabrication method therefor requires sintering a starting material at two stages in an oxidizing atmosphere and in a reducing atmosphere at relatively low temperatures. The starting material is either a powder mixture of uranium dioxide fresh material powder and triuranium octaoxide in a weight ratio of 75/25 ˜ 55/45 or pulverulent mixed uranium oxides yielding a final O/U ratio equal to that of the powder mixture. The sintering process in the oxidizing atmosphere involves at least one time period of a temperature rise to a higher temperature of 1200 to 1100° C. and at least one time period of a temperature drop to a lower temperature of up to 1080° C. A temperature difference between the higher and lower temperatures is preferred to be 50° C. or more.
摘要翻译：为了稳定地提供具有大粒径的二氧化铀烧结核燃料压块，其制造方法需要在氧化气氛中和在较低温度下的还原气氛中在两个阶段烧结原料。起始原料是二氧化铀新鲜材料粉末和三重态三氧化铀的重量比为75/25〜55/45的粉末混合物或粉末混合铀氧化物，得到与粉末混合物相同的最终O / U比。在氧化气氛中的烧结过程包括至少一个温度升高到1200至1100℃的较高温度的时间段和至少一个温度下降到最高1080摄氏度的较低温度的时间段。较高和较低温度之间的温度差优选为50℃或更高。

39. 发明授权

US5917875A Apparatus for inspecting nuclear fuel assemblies 失效
标题翻译：检查核燃料组件的装置
公开(公告)号：US5917875A
公开(公告)日：1999-06-29
申请号：US51219
申请日：1998-04-03
申请人： Barry Tuzio , Alan Blackwell
发明人： Barry Tuzio , Alan Blackwell
IPC分类号： G21C17/06 , G21C21/00
CPC分类号： G21C17/06 , G21C21/00 , G21Y2002/202 , G21Y2002/204 , G21Y2002/302 , G21Y2004/30 , G21Y2004/40 , G21Y2004/501
摘要： Apparatus for rectifying the tendency of a fuel assembly (1) to incline from the perpendicular has a top nozzle support (19) and a base assembly (18) for supporting, respectively, a top nozzle (7) and a bottom nozzle (2) of the fuel assembly. Incorporated in the base assembly is an elevating device (78, 79) which is operable to raise the fuel assembly. When raised, a grinding assembly (62) in the base assembly is able to remove material from the lower surfaces of the bottom nozzle so that they lie in a horizontal plane. The elevating device comprises a gimbal mounting arrangement which includes a gimbal (94) movably supported on a gimbal mount (88) by means of cooperating male and female spherically-shaped bearing surfaces. The grinding assembly includes a grinding wheel (66) which is mounted on a rotor (43) arranged for rotation about an axis along which the elevating device raises the fuel assembly so that material can be removed from each of the lower surfaces during one revolution of the rotor.
摘要翻译： PCT No.PCT / GB96 / 02346 Sec。 371日期：1998年4月3日 102（e）1998年4月3日PCT PCT 1996年9月24日PCT公布。出版物WO97 / 14155 日期1997年4月17日用于纠正燃料组件（1）从垂直方向倾斜的趋势的装置具有顶部喷嘴支撑件（19）和基座组件（18），用于分别支撑顶部喷嘴（7）和燃料组件的底部喷嘴（2）。结合在基座组件中的是可操作以升高燃料组件的升降装置（78,79）。当升起时，基座组件中的研磨组件（62）能够从底部喷嘴的下表面移除材料，使得它们位于水平面中。升降装置包括万向架安装装置，该万向架安装装置包括通过协同的凸形和凸形的球形支承表面可移动地支撑在万向架安装件（88）上的万向架（94）。研磨组件包括砂轮（66），该砂轮安装在转子（43）上，所述转轮（43）布置成围绕升降装置升起燃料组件的轴线旋转，使得材料可以在一周内从每个下表面移除转子。

40. 发明授权

US5882552A Method for recycling fuel scrap into manufacture of nuclear fuel pellets 失效
标题翻译：将燃料废料回收用于制造核燃料颗粒的方法
公开(公告)号：US5882552A
公开(公告)日：1999-03-16
申请号：US932602
申请日：1997-09-17
申请人： Kun-Woo Song , Keon-Sik Kim , Jong-Hun Kim , Youn-Ho Jung
发明人： Kun-Woo Song , Keon-Sik Kim , Jong-Hun Kim , Youn-Ho Jung
IPC分类号： G21C3/33 , C01G43/025 , C01G56/00 , G21C3/62 , G21C21/02 , G21C21/00
CPC分类号： G21C3/623 , C01G43/025 , C01G56/00 , C01P2002/54 , C01P2004/61 , C01P2006/10 , Y02E30/38
摘要： A method is disclosed in which fuel scrap of UO.sub.2 alone or UO.sub.2 containing an oxide of plutonium, gadolinium or erbium is recycled into the manufacture of nuclear fuel pellets. The fuel scrap consisting of defective fuel pellets is comminuted through oxidation to fuel particles of U.sub.3 O.sub.8 alone or U.sub.3 O.sub.8 containing an oxide of plutonium, gadolinium or erbium, and a sintering aid containing an element selected from the group consisting of aluminum, magnesium, niobium, titanium, vanadium, chromium, lithium, silicon, tin and mixtures thereof is added in a quantity of about 0.02% to about 2% by weight to the sintering powder which consists of said recycled fuel particles and fresh fuel powder having a composition of UO.sub.2 alone or UO.sub.2 in a mixture of PuO.sub.2, Gd.sub.2 O.sub.3 or Er.sub.2 O.sub.3. The sintering powder is then mixed uniformly, in which the amount of the recycled fuel particles is in the range of about 10% to about 100% by weight. Green pellets are made by pressing the sintering powder and then sintered at about 1500.degree. C. to about 1800.degree. C. in a reducing atmosphere to produce new fuel pellets.
摘要翻译：公开了一种方法，其中单独的UO2的燃料废料或含有钚，钆或铒的氧化物的UO2被再循环到核燃料颗粒的制造中。由有缺陷的燃料颗粒组成的燃料废料通过氧化粉碎成单独的U3O8的燃料颗粒或含有钚，钆或铒氧化物的U3O8，以及含有选自铝，镁，铌，钛的元素的烧结助剂，钒，铬，锂，硅，锡及其混合物的量以约0.02重量％至约2重量％的量加入到由所述再循环燃料颗粒和具有单独的UO2组成的新鲜燃料粉末组成的烧结粉末 UO2在PuO2，Gd2O3或Er2O3的混合物中。然后将烧结粉末均匀混合，其中再循环燃料颗粒的量在约10重量％至约100重量％的范围内。通过压制烧结粉末然后在还原气氛中在约1500℃至约1800℃下烧结生成颗粒，以产生新的燃料颗粒。

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