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51. 发明授权

US5303272A Apparatus for operating the grid springs of nuclear fuel assembly 失效
标题翻译：用于操作核燃料组件的电网弹簧的装置
公开(公告)号：US5303272A
公开(公告)日：1994-04-12
申请号：US964073
申请日：1992-10-21
申请人： Junichi Oyama , Akio Sando , Shuji Yamazaki
发明人： Junichi Oyama , Akio Sando , Shuji Yamazaki
IPC分类号： G21C21/00 , G21C3/334 , G21C19/00
CPC分类号： G21C3/334 , Y02E30/40
摘要： The present invention relates to an apparatus for manipulating the springs which hold the fuel rods firmly inside the grid cells of the grids in a nuclear fuel assembly. Conventionally fuel rods are inserted into the grids while the grid springs are in the active position, thus exposing the rods to possibilities of surface scratches and potential problems. The invented automatic apparatus avoids the formation of such surface damage on the fuel rods, by inserting the keys to inactivate the grid springs before inserting the fuel rods into the grids and removing the keys after all the rods are in place. The apparatus thus contributes to efficient manufacturing of the fuel assembly by simplifying the key quantity management operations and other tasks associated with the assembling operations.
摘要翻译：本发明涉及一种用于操纵弹簧的装置，其将燃料棒牢固地保持在核燃料组件中格栅的格栅内。通常，将燃料棒插入网格中，同时格栅弹簧处于活动位置，从而使杆暴露于表面划痕和潜在问题的可能性。本发明的自动装置通过在将燃料棒插入网格之前插入钥匙来灭活栅格弹簧并且在所有杆都到位之后去除钥匙，从而避免在燃料棒上形成这种表面损伤。因此，该装置有助于通过简化关键数量管理操作和与组装操作相关联的其他任务来有效地制造燃料组件。

52. 发明授权

US5289513A Method of making a fuel assembly lattice member and the lattice member made by such method 失效
标题翻译：制造燃料组件格子构件的方法和通过这种方法制成的格子构件
公开(公告)号：US5289513A
公开(公告)日：1994-02-22
申请号：US968011
申请日：1992-10-29
申请人： Edmund E. DeMario , Charles N. Lawson
发明人： Edmund E. DeMario , Charles N. Lawson
IPC分类号： G21C3/34 , G21C21/00
CPC分类号： G21C21/02 , G21C21/00 , G21C3/34 , G21C3/3424 , G21Y2002/302 , G21Y2004/30 , G21Y2004/40 , Y02E30/40
摘要： Method of making a fuel assembly lattice member and the lattice member made by such method. The method includes placing a plurality of elongate metal straps on a computer controlled conveyor which successively conveys the straps into alignment with each of a plurality of computer controlled piercing and drawing dies belonging to a progressive die machine. The dies are selectively actuated by the computer to form such elements as curved deflector vanes and spring members on each strap member. After the piercing and drawing operations are completed, the straps are joined by welding to form a lattice member of hexagonal cross section, the lattice member defining a plurality of rhombic-shaped fuel rod cells and a plurality of generally rhombic-shaped guide tube thimble cells therethrough. The rod cells are capable of receiving respective ones of a plurality of fuel rods and the thimble cells are capable of receiving respective ones of a plurality of thimble tubes. The rhombic shape of the rod cells cooperate with the deflector vanes to deflect a component of a fluid stream about the longitudinal center axis of each fuel rod for maintaining liquid substantially single-phase fluid flow over the surface of each fuel rod in order to avoid Departure from Nucleate Boiling (DNB) on the surface of the fuel rods.
摘要翻译：制造燃料组件格子构件的方法和通过这种方法制成的格子构件。该方法包括将多个细长的金属带放置在计算机控制的输送机上，该输送机连续地将带子与属于渐进式模具机的多个计算机控制的穿孔和拉伸模具中的每一个对准。模具由计算机选择性地致动以在每个带构件上形成诸如弯曲偏转叶片和弹簧构件的元件。在穿刺和拉伸操作完成之后，通过焊接将带子连接成六角形横截面的格子构件，格子构件限定多个菱形形状的燃料棒单元和多个大致菱形导向套管单元通过。杆单元能够接收多个燃料棒中的相应的燃料棒，并且套管单元能够接收多个顶针管中的相应的。杆状细胞的菱形与偏转叶片配合，以使流体流的分量围绕每个燃料棒的纵向中心轴线偏转，以使液体基本上单相流体流过每个燃料棒的表面，以避免出发来自核燃料（DNB）在燃料棒表面。

53. 发明授权

US5253278A Fuel assembly, channel box, production method of channel box, and core of nuclear reactor 失效
标题翻译：燃料组件，通道箱，通道箱的生产方法和核反应堆的核心
公开(公告)号：US5253278A
公开(公告)日：1993-10-12
申请号：US705723
申请日：1991-05-24
申请人： Toru Kanazawa , Osamu Yokomizo , Shin-ichi Kashiwai , Akihito Orii , Koji Nishida , Tatsuo Hayashi , Junjiro Nakajima
发明人： Toru Kanazawa , Osamu Yokomizo , Shin-ichi Kashiwai , Akihito Orii , Koji Nishida , Tatsuo Hayashi , Junjiro Nakajima
IPC分类号： G21C3/324 , G21C3/33 , G21C3/332 , G21C5/18 , G21C21/00 , G21C3/32
CPC分类号： G21C3/324 , G21C3/332 , G21Y2002/303 , G21Y2004/30 , Y02E30/40
摘要： A fuel assembly included a plurality of fuel rods, fuel spacers for maintaining gaps between the fuel rods and a channel box. The channel box includes spacer support portions projecting inwardly from an inner surface of the channel box and supporting the fuel spacer in a transverse direction and creep deformation inhibition portions disposed at the lower end portion of the channel box and projecting inwardly. The distance between the spacer support portions disposed to oppose one another in a horizontal direction is smaller than the distance between the creep deformation inhibition portions opposing one another in the horizontal direction.

54. 发明授权

US5048666A Nuclear fuel pellet transfer escalator 失效
标题翻译：核燃料颗粒转移自动扶梯
公开(公告)号：US5048666A
公开(公告)日：1991-09-17
申请号：US318107
申请日：1989-03-02
申请人： Thomas B. Huggins, Sr. , Elwyn Roberts , Melvin O. Edmunds
发明人： Thomas B. Huggins, Sr. , Elwyn Roberts , Melvin O. Edmunds
IPC分类号： G21C21/02 , B65G11/08 , B65G47/30 , B65G47/34 , B65G47/44 , B65G69/16 , F27B21/04 , F27D3/00 , F27D3/10 , F27D5/00 , G21C21/00
CPC分类号： F27D3/10 , B65G69/16 , F27D3/00 , G21C21/00 , F27B21/04 , F27D2003/0018 , F27D2003/0045 , F27D2003/0063 , F27D5/0068 , F27M2001/18
摘要： A pellet escalator in a pellet loading apparatus for loading nuclear fuel pellets from a pellet press into a sintering boat includes a conveyor in the form of an elongated arm for moving pellets and being pivotable to vertically move its discharge end toward and away from a sintering boat. The arm has an elongated recessed channel through which travels the upper run of an endless flexible conveying belt for transporting pellets from a receiving end to the discharge end of the conveyor. A chute is mounted to the arm at its discharge end and extends therebelow such that the chute is carried by the arm at its discharge end for vertical movement therewith toward and away from the sintering boat. Resiliently-flexible, deflectable bristled brushes are attached to the chute in opposing vertical rows. The brushes in one row are oppositely inclined and vertically offset from brushes in the other row for defining a gravity feed flow path of non-linear configuration between adjacent inner brush ends for transferring pellets downwardly through the chute along the flow path at a drop rate controlled by brush deflections. A stop finger mounted to the arm at its discharge end is actuatable between blocking and unblocking positions in which it respectively stops and permits pellet discharge from the upper run of the belt in the arm channel.

55. 发明授权

US4807734A Pellet-press-to-sintering-boat nuclear fuel pellet loading apparatus 失效
标题翻译：颗粒压机 - 烧结船核燃料颗粒装载装置
公开(公告)号：US4807734A
公开(公告)日：1989-02-28
申请号：US77347
申请日：1987-07-24
申请人： Fred S. Breeland, Jr. , Thomas B. Huggins
发明人： Fred S. Breeland, Jr. , Thomas B. Huggins
IPC分类号： G21C21/02 , B65G11/20 , F27B21/04 , F27D3/00 , F27D3/10 , F27D5/00 , G21C21/00 , B65G47/44
CPC分类号： G21C21/00 , B65G11/203 , F27D3/00 , F27B21/04 , F27D2003/0018 , F27D3/10 , F27D5/0068 , F27M2001/18 , Y10S198/956
摘要： Apparatus for loading friable nuclear fuel pellets into a sintering boat from a pellet press which ejects newly made pellets. An inclined pellet chute (preferably a tube) receives the ejected pellets and discharges them against a first resilient brush which reflects the pellets downwardly to a second resilient brush. The brush tips are spaced apart such that a pellet moving downward along the second brush contacts the flexible brush tip of the first brush before dropping off the second brush (preferably with near-zero velocity) into the sintering boat.

56. 发明授权

US4800061A Apparatus for loading fuel rods into grids of nuclear fuel assemblies 失效
标题翻译：用于将燃料棒装载到核燃料组件的网格中的装置
公开(公告)号：US4800061A
公开(公告)日：1989-01-24
申请号：US46475
申请日：1987-05-06
申请人： John M. Shallenberger , Stephen J. Ferlan
发明人： John M. Shallenberger , Stephen J. Ferlan
IPC分类号： G21C21/00 , G21C3/334
CPC分类号： G21C3/334 , Y02E30/40 , Y10T29/531
摘要： The invention relates to apparatus and a method for facilitating a scratchless insertion of a fuel rod into cellular grids of a nuclear fuel assembly.The apparatus comprises a thin-walled tubular member having an inner diameter substantially corresponding to the outer diameter of a fuel rod, and having a longitudinal slit formed in its wall so as to render the latter resiliently deflectable in a diameter-reducing sense. The method comprises the steps of mounting the thin-walled tubular member in position for protectively enveloping the fuel rod during insertion thereof; inserting the fuel rod into the grids while the tubular member is in place to envelope it; and withdrawing the tubular member from the inserted fuel rod.
摘要翻译：本发明涉及用于促进将燃料棒无油地插入核燃料组件的蜂窝格栅中的装置和方法。该装置包括薄壁管状构件，其具有基本上对应于燃料棒的外径的内径，并且在其壁中形成有纵向狭缝，以使后者能够以直径减小的方式弹性地偏转。该方法包括以下步骤：将薄壁管状构件安装在适当位置，以便在其插入期间保护性地包围燃料棒; 将燃料棒插入网格中，同时管状构件就位以将其包围; 以及从插入的燃料棒中取出管状构件。

57. 发明授权

US4772446A Gripper assembly for inserting and removing burnable absorber rods and thimble plugs in a nuclear reactor fuel assembly 失效
标题翻译：用于在核反应堆燃料组件中插入和移除可燃吸收棒和套筒塞的夹具组件
公开(公告)号：US4772446A
公开(公告)日：1988-09-20
申请号：US932244
申请日：1986-11-19
申请人： Robert E. Meuschke
发明人： Robert E. Meuschke
IPC分类号： G21C21/00 , G21C3/334 , G21C19/105 , G21C19/10
CPC分类号： G21C3/334 , G21C19/105 , G21Y2002/201 , G21Y2002/302 , G21Y2002/304 , G21Y2004/30 , G21Y2004/403 , G21Y2004/501 , Y02E30/40 , Y10S294/906 , Y10T29/531 , Y10T29/53657
摘要： Apparatus for releasably engaging an elongated member that is releasably connected to the top nozzle of a nuclear reactor fuel assembly. The top nozzle has an adapter plate disposed at its lower end having at least one passageway therethrough through which the elongated member is disposed. The elongated member has a releasable latching structure at one end that is able to be engaged by the apparatus, having at least one latching member movable between a latched position in which the latching member is able to engage said adapter plate and secure the absorber rod in a stationary relationship with respect to the adapter plate and an unlatched position in which the latching member is able to disengage from said adapter plate so that the elongated member be removed from the fuel assembly. The apparatus comprises a hollow releasing member for moving the latching member of the latching structure between its latched position and its unlatched position, an engaging member connected to the releasing member and extending downwardly through the hollow portion of the releasing member, and an actuating member extending downwardly through the hollow portion of the releasing member and coacting with the engaging member to releasably engage the latching structure.
摘要翻译：用于可释放地接合可释放地连接到核反应堆燃料组件的顶部喷嘴的细长构件的装置。顶部喷嘴具有设置在其下端的适配器板，其具有穿过其中的至少一个通道，细长构件通过该通道布置。细长构件在一端具有可释放的闩锁结构，其能够被该装置接合，具有至少一个闩锁构件，该锁定构件可在闩锁位置之间移动，在闩锁位置中闩锁构件能够接合所述适配器板并将吸收杆固定在相对于适配器板的固定关系和解锁位置，其中闩锁构件能够与所述适配器板脱离，使得细长构件从燃料组件移除。该装置包括中空释放构件，用于将闩锁构件的闩锁构件在其闩锁位置和其解锁位置之间移动;接合构件，其连接到释放构件并向下延伸穿过释放构件的中空部分;以及致动构件，向下穿过释放构件的中空部分并与接合构件共同作用以可释放地接合闩锁结构。

58. 发明授权

US4762665A Stack forming apparatus 失效
标题翻译：堆叠成型装置
公开(公告)号：US4762665A
公开(公告)日：1988-08-09
申请号：US914628
申请日：1986-10-02
申请人： Alan J. Billington , Thomas G. Rice
发明人： Alan J. Billington , Thomas G. Rice
IPC分类号： B07C5/36 , G21C21/02 , G21C21/00 , B65B5/10
CPC分类号： G21C21/02 , Y10T29/531
摘要： Bodies such as nuclear fuel pellets are formed into a stack in a stacking lane (34) and the length of the stack is measured at intervals by device (40) to determine if the partly-formed stack is drifting away from a target length. Pellets are issued into the stacking zone (34) by a selector mechanism (32), the input of which receives pellets from three lanes (24, 26, 28) containing oversize, undersize and intermediate size pellets and the pellets issued to the stacking lane (34) are selected under the control of microprocessor-based unit (18) according to the extent of any drift from the target value. The pellets in lanes (24, 26, 28) are derived from a common supply (12) following segregation by a diverter mechanism (22) controlled by unit (18) in accordance with length measurements made by measuring device (16).
摘要翻译：诸如核燃料颗粒的机体在堆叠通道（34）中形成堆叠，并且由设备（40）间隔地测量堆叠的长度，以确定部分形成的堆叠是否远离目标长度漂移。颗粒通过选择器机构（32）被输送到堆叠区域（34）中，选择器机构（32）的输入从三个通道（24,26,28）接收包含超大尺寸，尺寸过小的和中等尺寸的颗粒的颗粒，并且将颗粒发送到堆叠通道（34）在基于微处理器的单元（18）的控制下根据从目标值的漂移程度来选择。通道（24,26,28）中的颗粒源自通过根据由测量装置（16）进行的长度测量由单元（18）控制的分流机构（22）分离之后的共同供应源（12）。

59. 发明授权

US4678924A Method of setting a stop means inside of a tubular element 失效
标题翻译：在管状元件内部设置止动装置的方法
公开(公告)号：US4678924A
公开(公告)日：1987-07-07
申请号：US751431
申请日：1985-07-03
申请人： Pierre Loriot , Michel Rendu , Jean Rousseau , Alain Samoel
发明人： Pierre Loriot , Michel Rendu , Jean Rousseau , Alain Samoel
IPC分类号： G21C3/16 , G21C3/18 , G21C21/00
CPC分类号： G21C3/18 , G21C3/16 , G21Y2002/302 , G21Y2002/303 , G21Y2004/30 , G21Y2004/40 , Y02E30/40 , Y10T29/4978 , Y10T29/49861 , Y10T29/49929
摘要： Fuel and fertile rod for a nuclear reactor. It comprises a can, a column of fissile and/or fertile pellets within the can and end plugs welded to the two ends of the can. The column of pellets is held in place by two tubular spacers of limited thickness and with rounded edges abutting against the two ends of the fuel column and set with a fixed dimension to the can. The column of fissile and fertile pellets can also be held in place by a supplementary positioning setting of the fertile pellet column.
摘要翻译：用于核反应堆的燃料和肥沃的棒。它包括一罐罐，容器内的易裂变和/或可育颗粒，罐内端部焊接的端部塞子。丸粒的柱通过两个有限厚度的管状隔离物保持在适当的位置，并且圆形边缘抵靠燃料柱的两端并且以固定的尺寸设置在罐上。易裂变和可育颗粒的柱子也可以通过肥沃颗粒柱的补充定位来保持在适当位置。

60. 发明授权

US4676935A Method of producing mixed-oxide nuclear fuel pellets soluble in nitric acid 失效
标题翻译：生产可溶于硝酸的混合氧化物核燃料颗粒的方法
公开(公告)号：US4676935A
公开(公告)日：1987-06-30
申请号：US775701
申请日：1985-09-13
申请人： Peter Funke , Dietmar Hanus , Rainer Lob , Wihelm Konigs
发明人： Peter Funke , Dietmar Hanus , Rainer Lob , Wihelm Konigs
IPC分类号： B01J2/14 , B02C23/06 , G21C3/62 , G21C21/00 , G21C19/42 , G21C19/44
CPC分类号： G21C3/623 , Y02E30/38
摘要： Production of mixed-oxide nuclear fuel pellets of uranium dioxide (UO.sub.2+x) and plutonium dioxide (PuO.sub.2) which are soluble in nitric acid. The powder mixture of oxides is added to a halogen-free milling aid, such as propane diol, then is milled and subsequently granulated, pressed and sintered. The milling aid is expelled by subsequent drying processes or heat treatments (sintering). The milling process is controlled to obtain a primary grain size of less than two micrometers.
摘要翻译：生产可溶于硝酸的二氧化铀（UO2 + x）和二氧化钚（PuO2）的混合氧化物核燃料颗粒。将氧化物的粉末混合物加入到无卤素研磨助剂如丙二醇中，然后研磨并随后造粒，压制和烧结。研磨助剂通过随后的干燥过程或热处理（烧结）排出。控制研磨过程以获得小于2微米的初级粒度。

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