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    • 73. 发明授权
    • Enclosing a gas in a nuclear reactor fuel rod
    • 在核反应堆燃料棒中包围气体
    • US4570051A
    • 1986-02-11
    • US449108
    • 1982-12-13
    • Nobuo Miwa
    • Nobuo Miwa
    • B23K9/028G21C21/00G21C21/02B23K9/225
    • G21C21/00B23K9/028
    • A method and system for enclosing a gas at a preselected pressure in a nuclear reactor fuel rod having two ends open to its interior. Hermetically enclose each end in a separate airtight chamber. Introduce the gas into the first chamber and open the second chamber to purge the fuel rod interior and both chambers of residual atmosphere. After purging close the open second chamber and determine the gas pressure in the fuel rod interior. When the pressure reaches the preselected value, hermetically seal each fuel rod end while in its respective chamber. After sealing, remove the fuel rod from the chambers.
    • 一种用于在预反应的压力下封闭气体的方法和系统,该核反应堆燃料棒的两端开放到其内部。 将每一端密封在一个独立的气密室中。 将气体引入第一个室并打开第二个室,以清除燃料棒内部和两个室的残留气氛。 吹扫关闭开放的第二室并确定燃料棒内部的气体压力。 当压力达到预选值时,在其各自的室内气密地密封每个燃料棒端。 密封后,将燃料棒从室中取出。
    • 75. 发明授权
    • Encapsulated fuel unit and method of forming same
    • 封装燃料单元及其形成方法
    • US4500488A
    • 1985-02-19
    • US415117
    • 1982-09-07
    • Edward F. GrohDale A. CassidyEdward F. Lewandowski
    • Edward F. GrohDale A. CassidyEdward F. Lewandowski
    • G21C3/04G21C21/02
    • G21C21/02G21C3/04Y02E30/40Y10S376/903
    • This invention teaches an encapsulated fuel unit for a nuclear reactor, such as for an enriched uranium fuel plate of thin cross section of the order of 1/64 or 1/8 of an inch and otherwise of rectangular shape 1-2 inches wide and 2-4 inches long. The case is formed from (a) two similar channel-shaped half sections extended lengthwise of the elongated plate and having side edges butted and welded together to define an open ended tube-like structure and from (b) porous end caps welded across the open ends of the tube-like structure. The half sections are preferably of stainless steel between 0.002 and 0.01 of an inch thick, and are beam welded together over and within machined and hardened tool steel chill blocks. The porous end caps preferably are of T-316-L stainless steel having pores of approximately 3-10 microns size.
    • 本发明教导了用于核反应堆的封装燃料单元,例如1/16英寸或1/8英寸量级的薄横截面的富铀燃料板,另外还有矩形形状为1-2英寸宽和2 -4英寸长。 壳体由(a)两个类似的通道形半部分形成,该两个相似的通道状半部分在细长板的纵向上延伸并且具有对接并焊接在一起的侧边缘以限定开口的管状结构,并且从(b)跨越开口焊接的多孔端盖 管状结构的端部。 半部分优选为0.002和0.01英寸厚之间的不锈钢,并且在加工和硬化的工具钢冷却块之间和内部被束缚在一起。 多孔端盖优选为具有约3-10微米尺寸的孔的T-316-L不锈钢。
    • 78. 发明授权
    • Process for the production of block fuel elements for high temperature
reactors
    • 生产用于高温反应堆的块状燃料元件的方法
    • US4140738A
    • 1979-02-20
    • US774953
    • 1977-03-07
    • Milan HrovatLothar Rachor
    • Milan HrovatLothar Rachor
    • C04B35/532G21C3/64G21C21/02G21C21/00
    • G21C3/64C04B35/532G21C21/02Y02E30/33Y02E30/38
    • There is provided a process for the production of block fuel elements for gas cooled high temperature reactors by multiple step molding of a granulated graphite material comprising a mixture of natural graphite powder, synthetic graphite powder and binder resin together with coated fissile and fertile fuel particles using a lubricant and a hydrocarbon, alcohol, phenol, amine, aldehyde, ketone or ether as an air displacing agent whereby the outer form and the cooling gas channels are produced by molding and the molding temperature in the last molding step is above the softening point of the binder resin and wherein the binder resin is so chosen that it has a softening point at least 15.degree. C above the melting point of the lubricant used and the block is ejected from the die in the temperature interval between the melting point of the lubricant and the softening point of the binder resin.
    • 提供了一种用于气体冷却的高温反应器的块状燃料元件的制造方法,该方法是通过将包含天然石墨粉末,合成石墨粉末和粘合剂树脂的混合物的粉末状石墨材料与涂覆的易裂变和可燃的燃料颗粒 润滑剂和烃,醇,酚,胺,醛,酮或醚作为空气移动剂,由此通过模塑制备外部形式和冷却气体通道,并且最后成型步骤中的成型温度高于 粘合剂树脂,其中粘合剂树脂被选择为具有高于所用润滑剂的熔点至少15℃的软化点,并且在润滑剂的熔点和 粘合剂树脂的软化点。
    • 79. 发明授权
    • Method of joining nuclear fuel rod end caps and nuclear fuel rod
cladding tubes
    • 连接核燃料棒端盖和核燃料棒包层管的方法
    • US4097712A
    • 1978-06-27
    • US739640
    • 1976-11-08
    • Helmut Bezold
    • Helmut Bezold
    • G21C21/02B23K11/02B23K11/04G21C3/10
    • G21C3/10B23K11/04Y02E30/40
    • Method of joining fuel rod end caps and cladding tubes by resistance pressure welding within a welding chamber. A welding device is brought into engagement with an end portion of a rigidly mounted cladding tube. An opening chuck as well as a divided welding electrode, both of which are mounted at one side of the welding chamber, are shifted along a predetermined length of the cladding tube end portion. The chuck and the divided welding electrode are brought into contact with the cladding tube end portion. Another welding electrode carrying and end cap is thrust into the welding chamber from the other side thereof so that the end cap is fed to the open end of the cladding tube end portion. The welding chamber is sealed by sealing members sealingly engaging the cladding tube end portion and the other welding electrode and then the interior of the welding chamber is evacuated and filled with protective gas. The end cap is pressed onto the open end of the cladding tube end portion. A welding current is passed through the welding electrodes so as to weld the end cap to the end of the cladding tube end portion.
    • 通过焊接室内的电阻压力焊接燃料棒端盖和包层管的方法。 焊接装置与刚性安装的包层管的端部接合。 两个安装在焊接室一侧的分开的焊接电极沿包层管端部的预定长度移动。 卡盘和分割焊接电极与包层管端部接触。 另一个焊接电极承载和端盖从另一侧推入焊接室,使得端盖被馈送到包层管端部的开口端。 焊接室由与包层管端部和其他焊接电极密封接合的密封部件密封,然后将焊接室的内部抽真空并填充有保护气体。 将端盖压到包层管端部的开口端。 焊接电流通过焊接电极,以将端盖焊接到包层管端部的端部。
    • 80. 发明授权
    • Method of making ZrH fuel element
    • 制造ZrH燃料元素的方法
    • US4071587A
    • 1978-01-31
    • US616584
    • 1975-09-25
    • George H. Eggers
    • George H. Eggers
    • G21C21/02G21C21/00
    • G21C21/02
    • A method of making a nuclear fuel element for a fission reactor. A solid body of an alloy of zirconium and nuclear fuel metal is exposed to hydrogen at an elevated temperature to hydride the zirconium. The hydrided alloy is exposed to oxygen at a lower temperature to form a continuous oxide layer about its exterior surface and is employed in a gastight container as a fuel element. The hydrided alloy may be exposed to oxygen at a temperature of at least about 300.degree. C. prior to its enclosure in the container, or the hydrided alloy may be enclosed in the container together with a quantity of an oxygen-providing material, such as CO.sub.2 or H.sub.2 O, sufficient to oxidize its exterior surface when the fuel element is raised to an elevated temperature.
    • 制造裂变反应堆核燃料元件的方法。 锆和核燃料金属的合金的固体在升高的温度下暴露于氢气以氢化锆。 氢化合金在较低温度下暴露于氧气以在其外表面周围形成连续的氧化物层,并且用作气体容器中的燃料元件。 氢化合金在其封闭在容器中之前可以在至少约300℃的温度下暴露于氧气,或者将氢化合金与一定数量的供氧材料一起封闭在容器中,例如 CO 2或H 2 O,当燃料元件升高到高温时足以氧化其外表面。