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91. 发明授权

US3890413A Apparatus and method for compacting particulate materials 失效
标题翻译：用于压实颗粒材料的装置和方法
公开(公告)号：US3890413A
公开(公告)日：1975-06-17
申请号：US49757374
申请日：1974-08-15
申请人： HYDRAMET AMERICAN INC
发明人： PETERSON WILLIAM M
IPC分类号： G21C21/02 , B29C33/00 , B29C43/00 , B29C43/04 , B29C43/10 , B29C43/14 , B29C43/34 , B29C43/36 , B29C43/50 , B29C43/58 , B30B11/02 , B30B11/04 , B30B15/06
CPC分类号： B30B11/04 , B30B15/067
摘要： Power in a plurality of die cavities is compacted by a corresponding plurality of punches on a head, each punch being connected with a piston in a hydraulic cylinder on the head. The cylinders communicate with each other and with a hydraulic accumulator cylinder which permits the punches individually to shift axially and compensate for cavity-to-cavity variations in the amount of powder fill. When the head moves beyond the range in which compensation occurs, a piston in the accumulator bottoms out to build equal pressure in the cylinders to transmit uniform compacting force to the punches.
摘要翻译：在多个模腔中的动力由头部上相应的多个冲头压实，每个冲头与头上的液压缸中的活塞连接。气缸彼此连通并且具有液压蓄能器缸，其允许冲头单独地轴向移动并补偿空腔到空腔中粉末填充量的变化。当头部移动超过补偿发生的范围时，蓄能器中的活塞底部流出，以在气缸中形成相等的压力，以向冲头传递均匀的压实力。

92. 发明授权

US3855061A Nuclear reactor fuel plate 失效
标题翻译：核反应堆燃料板
公开(公告)号：US3855061A
公开(公告)日：1974-12-17
申请号：US15501471
申请日：1971-06-21
申请人： GRACE W R & CO
发明人： TRIGGIANI L , SANCHEZ M , ASHBY G
IPC分类号： G21C3/16 , G21C3/36 , G21C21/02 , G21C3/30
CPC分类号： G21C3/16 , G21C3/36 , G21C21/02 , Y02E30/40
摘要： An improved nuclear fuel element which comprises an ordered array of spherical fuel particles dispersed in a flat plate; and the use of this fuel element to render improved heat transfer characteristics to nuclear reactor systems.
摘要翻译：一种改进的核燃料元件，其包括分散在平板中的球形燃料颗粒的有序阵列; 并且使用这种燃料元件来改善对核反应堆系统的传热特性。

93. 发明授权

US3833470A Method of making fuel and fertile elements for nuclear-reactor cores 失效
标题翻译：制造核反应堆燃料和有效元素的方法
公开(公告)号：US3833470A
公开(公告)日：1974-09-03
申请号：US25003272
申请日：1972-05-03
申请人： KERNFORSCHUNGSANLAGE JUELICH
发明人： GYARMATI E , NICKEL H
IPC分类号： G21C3/04 , G21C3/62 , G21C3/64 , G21C3/26 , G21C21/02
CPC分类号： G21C3/62 , G21C3/044 , G21C3/626 , G21C3/64 , Y02E30/33 , Y02E30/38
摘要： Fissionable-fuel or fertile elements for the core of a nuclear reactor, especially a reactor of the gas-cooled type, wherein the fuel or fertile material is introduced into graphite shells in the form of coated particles and a pyrolytically decomposable carbon-containing or silane gas is passed upwardly through the shell while the mass therein is heated by displacing an induction-furnace core downwardly around the graphite shell thereby bonding the coated particles together with pyrolytic carbon, silicon carbide or zirconium carbide being formed in situ to yield a coherent mass with a porosity of, say, 10 to 25 percent. The gas is preferably a mixture of one or more inert gases (nitrogen, argon or helium) with one or more hydrocarbons or carbon-containing gases (e.g., methane, acetylene, benzene, or silanes).
摘要翻译：用于核反应堆，特别是气冷式反应器的核心的可裂变燃料或可育元素，其中将燃料或可食用材料以涂覆颗粒的形式引入石墨壳中，并将可热分解的含碳或硅烷气体通过壳体向上通过，同时通过将感应炉芯向下移动到石墨壳体上来加热其中的质量，从而将涂覆的颗粒与热解碳，碳化硅或碳化锆原位形成，以产生具有孔隙率例如为10％至25％。气体优选是一种或多种惰性气体（氮气，氩气或氦气）与一种或多种烃或含碳气体（例如甲烷，乙炔，苯或硅烷）的混合物。

94. 发明授权

US3832222A Chemical vapor deposition of uranium and plutonium 失效
标题翻译：铀和钚的化学气相沉积
公开(公告)号：US3832222A
公开(公告)日：1974-08-27
申请号：US31880772
申请日：1972-12-27
申请人： ATOMIC ENERGY COMMISSION
发明人： CRISLER L , EGGERMAN W
IPC分类号： C23C16/18 , G21C21/02 , C23C11/02
CPC分类号： C23C16/18 , G21C21/02 , Y10S376/901
摘要： URANIUM (U) OR PLUTONIUM (PU) IS DEPOSITED UPON A SUBSTRATE BY VAPORIZING TRISCYCLOPENTADIENYLURANIUM (IV) CHLORIDE (CP2UCI) OR PLUTONIUM (III) TRICYCLOPENTADIENIDE (PUCP3), HEATING THE SUBSTRATE UPON WHICH THE PU OR U IS TO BE DEPOSITED TO FROM ABOUT 600*C. TO ABOUT 900*C., AND CONTACTING THE VAPORIZED COMPOUND WITH THE HEATED SUBSTRATE TO DEPOSIT A COATING OF U OR PU RESPECTIVELY.

95. 发明授权

US3823067A Shaped nuclear fissionable bodies 失效
标题翻译：形状的核可变体
公开(公告)号：US3823067A
公开(公告)日：1974-07-09
申请号：US16810771
申请日：1971-08-02
申请人： UNITED NUCLEAR CORP
发明人： STERN G , ROCHE W
IPC分类号： G21C3/16 , G21C3/62 , G21C21/02 , G21C3/04
CPC分类号： G21C3/16 , G21C3/623 , G21C21/02 , Y02E30/38 , Y10S376/903
摘要： SHAPED NUCLEAR FUEL PELLETS FOR USE IN ROD-TYPE FUEL ELEMENTS AND PARTICULARLY SHAPED FUEL PELLETS FORMED BY SINTERING FISSIONABLE POWDERED MATERIALS.

96. 发明授权

US3808145A Ceramic defluorination and reduction process 失效
标题翻译：陶瓷定义和还原过程
公开(公告)号：US3808145A
公开(公告)日：1974-04-30
申请号：US19537471
申请日：1971-11-03
申请人： GEN ELECTRIC
发明人： PACKARD D , MARLOWE M
IPC分类号： C01G43/01 , C01G43/025 , G21C3/00 , G21C21/02 , C01G43/02
CPC分类号： C01G43/025 , C01P2006/12 , C01P2006/13 , C01P2006/80
摘要： A PROCESS FOR DEFLUORINATING AND CONTROLLING THE OXYGENTO-METAL RATION OF A PARTICULATE COMPOSITION CONTAINING URANIUM COMPOUNDS IS CONDUCTED AT A TEMPERATURE IN THE RANGE OF ABOUT 200 TO ABOUT 800*C. IN AN ATMOSPHER HAVING THE ESSENTIAL COMPONENTS OF WATER VAPOR WHICH ACTS AS LOW TEMPERATURE DEFLUORINATION AGENT AND A CARRIER GAS OF CONTROLLED OXYGEN PARTIAL PRESSURE. THE CARRIER GAS CAN BE A MIXTURE COMPRISING HYDROGEN AND CARRIER DIOXIDE, A MIXTURE COMPRISING CARBON MONOXIDE AND CARBON DIOXIDE, AND MIXTURE COMPRISING AN INERT GAS CONTAINING UP TO ABOUT 10 PARTS PERMILLION OXYGEN AND A SOURCE OF HYDROGEN. THE INTRODUCTION OF WATER VAPOR GREATLY IMPROVES THE REMOVLA OF FLUORIDE IONS AT TEMPERATURES BELOW THE TEMPERATURES AT WHICH OXYGEN REMOVAL FROM THE PARTICULATE COMPOSITION OCCURS. THIS PROCESS HAS TWO STAGES WITH THE FIRST LOWER TEMPERATURE STAGE GIVING SUBSTANTIAL REMOVAL OF FLUORIDE IONS AND THE SECOND HIGHER TEMPERATURE STAGE GIVING A SUBSTANTIAL PORTION OF THE OXYGEN REMOVAL FOR CONTROLLING THE OXYGEN-TO-METAL RATIO OF THE PARTICULATE COMPOSITON.

97. 发明授权

US3803273A Ceramic fuel fabrication process providing controlled density and grain size 失效
标题翻译：陶瓷燃料制造过程提供控制密度和粒度
公开(公告)号：US3803273A
公开(公告)日：1974-04-09
申请号：US17574671
申请日：1971-08-27
申请人： GEN ELECTRIC
发明人： HILL H , KAZNOFF A , MARLOWE M
IPC分类号： G21C3/62 , G21C21/02
CPC分类号： G21C3/62 , Y02E30/38
摘要： A METHOD FOR FABRICATING CERAMIC FUEL HAVING CONROLLED DENSITY AND GRAIN SIZE IS DESCRIBED. CERAMIC POWDERS OF ANY GIVEN INITIAL GRAIN SIZE ARE SUBJECTED TO FORMING PRESSURES TO PRODUCE A STRUCTURE OF DESIRED CONFIGURATION FOLLOWED BY HIGH TEMPERATURE SINTERING TO GIVE CONTROLLED GRAIN GROWTH AND TO FORM A SOLID STRUCTURE. THE STRUCTURE IS THEN DISINTEGRATED BY SUITABLE MEANS INCLUDING A CYCLIC OXIDATIN-REDUCTION SEQUENCE TO SEPARATE THE GRAINS ALONG GRAIN BOUNDARIES THUS PRESERVING THE SIZE AND IDENTITY OF THE GRAINS OF THE CERAMIC FUEL. THE GRAINS ARE SUBJECTED TO FORMING PRESSURES TO PRODUCE A STRUCTURE OF DESIRED CONFIGURATION AND SUBJECTED TO A HIGH TEMPERATURE SINTERING TO ACHIEVE A SOLID BODY. THE INVENTION IS APPLICABLE TO CERAMICS SUCH AS URANIUM DIOXIDE AND OTHER COMPOUNDS OF MULTIVALENT CATIONS.

98. 发明授权

US3801451A Ceramic nuclear fuel or breeder material tablets and method of producing the same 失效
标题翻译：陶瓷核燃料或烧烤料材料片及其制造方法
公开(公告)号：US3801451A
公开(公告)日：1974-04-02
申请号：US3801451D
申请日：1972-02-14
申请人： SIEMENS AG
发明人： SCHARF H
IPC分类号： G21C3/28 , G21C21/02 , G21C3/02 , G21C3/30
CPC分类号： G21C3/28 , G21C21/02 , Y02E30/40
摘要： Ceramic fissionable fuel or breeder material tablet axially alignable with corresponding tablets for forming nuclear reactor fuel rods includes a substantially cylindrical member having a depression at opposite end faces thereof, the end faces respectively comprising a marginal zone of slightly sloping conical shape having an angle of inclination within a range of 0.5* to 30*, the inclined marginal zone defining, with the remaining surface of the respective end face, an annular contact edge for contacting an end face of another tablet axially alignable therewith, the annular contact edge being spaced from the peripheral edge of the end face a given distance so that compression forces acting on the annular contact edge when the tablet is in use in a nuclear reactor fuel rod, are absorbable by a spatial region of the table having adequate strength for absorbing the compression forces.

99. 发明授权

US3757396A Production apparatus for nuclear reactor fuel rods 失效
标题翻译：生产装置用于核反应堆燃料炉
公开(公告)号：US3757396A
公开(公告)日：1973-09-11
申请号：US3757396D
申请日：1971-08-18
申请人： SIEMENS AG
发明人： LOHRBACH W
IPC分类号： G21C21/02 , G21C21/00 , B23P25/00
CPC分类号： G21C21/02 , Y10T29/5199
摘要： When machining, filling and cleansing casing tubes in the production of reactor fuel rods, the latter are disposed in a closed container and held therein in support tubes. Individual processing equipment is located at one face of the container while, at the other face thereof, a rotary shaft provided with grippers, drives for displacing the support tubes into the individual processing position and drives of clamping devices for the support tubes are provided. Consequently, only parts having a smooth surface and being relatively easy to decontaminate are present in the interior of the container.
摘要翻译：当在反应堆燃料棒的生产中加工，填充和清洗套管时，将后者设置在密闭的容器中并保持在支撑管中。单独的加工设备位于容器的一个面上，而在其另一个面上设置有设置有夹持器的旋转轴，用于将支撑管移动到各个处理位置的驱动装置和用于支撑管的夹紧装置的驱动。因此，只有具有光滑表面并且相对容易净化的部件才存在于容器的内部。

100. 发明授权

US3725635A Method of and apparatus for welding an end plug onto a nuclear fuel element 失效
标题翻译：用于将末端焊接焊接到核燃料元件上的方法和装置
公开(公告)号：US3725635A
公开(公告)日：1973-04-03
申请号：US3725635D
申请日：1971-08-20
申请人： WESTINGHOUSE ELECTRIC CORP
发明人： FINK R , BOYKO E
IPC分类号： B23K9/00 , B23K10/02 , G21C3/10 , G21C21/02
CPC分类号： B23K10/02 , G21C3/10 , Y02E30/40
摘要： Welding methods and apparatus for bonding a metallic end plug into an end of a metallic fuel tube or rod for a nuclear reactor. Defects in the weld joint between the fuel tube and end plug are substantially reduced by arc welding in a chamber filled with an inert gas, disposing the welding electrode directly over the joint to be welded, deflecting plasma produced during the welding away from the body of the fuel tube, and directing the plasma into the joint.
摘要翻译：用于将金属端塞接合到用于核反应堆的金属燃料管或杆的端部中的焊接方法和装置。燃料管和端塞之间的焊接接头的缺陷通过在填充有惰性气体的室中的电弧焊接大大减少，将焊接电极直接设置在要焊接的接头上，使焊接期间产生的等离子体远离主体燃料管，并将等离子体引导到接头中。

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