利索-全球专利检索

  1. 登录
  2. 注册

搜索结果

18 条记录 (耗时 0.013 秒)

    Fuel assembly with channel box
    2.
    发明公开
    Fuel assembly with channel box 无效
    BrennstoffbündelmitStrömungskanal。

    公开(公告)号：EP0501259A1

    公开(公告)日：1992-09-02

    申请号：EP92102529.2

    申请日：1992-02-14

    申请人： HITACHI, LTD. ,  Hitachi Engineering Co., Ltd.

    发明人： Yanagi, Yoshihiko ,  Nakajima, Junjiro ,  Kanamori, Kenji ,  Umehara, Hajime ,  Aizawa, Yasuhiro ,  Sakuma, Toraki ,  Hirakawa, Hiromasa ,  Ishizaki, Hideaki

    IPC分类号： G21C3/324

    CPC分类号： G21C3/324 ,  G21Y2002/201 ,  G21Y2002/303 ,  G21Y2004/30 ,  Y02E30/40

    摘要： A fuel assembly comprises a plurality of fuel rods (3) supported by an upper tie plate (7) and a lower tie plate (8) respectively at each of upper end portion and lower end portion, and a channel box (2, 2A) surrounding a bundle of the fuel rods (3) and the lower tie plate (8). The fuel assembly forms a natural uranium region at lower end portion of effective fuel length portion. A wall thickness at a lower thick wall region of the channel box (2, 2A) is thicker than the wall thickness at a region locating upward from the lower thick wall region and between corner portions of the channel box. Upper end of the lower thick wall region locates upward from upside of the lower tie plate and downward from upper end of the natural uranium region. A wall thickness at the corner portion of the channel box (2, 2A) is thicker than the wall thickness at middle portion of said wall between the corner positions at the region locating upward from the lower thick wall region.
    The fuel assembly is able to reduce stresses caused in the channel box (2, 2A) in an earthquake, and, is able to improve fuel economy.

    摘要翻译： 燃料组件包括分别在上端部分和下端部分中的上连接板（7）和下连接板（8）支撑的多个燃料棒（3）和通道箱（2,2A） 围绕一束燃料棒（3）和下连接板（8）。 燃料组件在有效燃料长度部分的下端部分形成天然铀区域。 在通道箱（2,2A）的较低厚壁区域处的壁厚比在下壁厚壁区域和通道箱的拐角部分之间的区域处的壁厚厚。 下部厚壁区域的上端位于下部连接板的上侧，并从天然铀区域的上端向下。 在通道箱（2,2A）的角部处的壁厚比在下壁厚区域上方的区域的角位置之间的壁的中间部分处的壁厚更厚。 燃料组件能够减少地震中通道箱（2,2A）中产生的应力，并且能够提高燃油经济性。

    A method of producing composite nuclear fuel cladding
    4.
    发明公开
    A method of producing composite nuclear fuel cladding 失效
    Verfahren zur Beschichtung vonKernbrennelementhüllenrohren。

    公开(公告)号：EP0210486A1

    公开(公告)日：1987-02-04

    申请号：EP86109381.3

    申请日：1986-07-09

    申请人： HITACHI, LTD.

    发明人： Matsumoto, Toshihiro ,  Umehara, Hajime ,  Nakajima, Junjiro ,  Fujii, Norihisa

    IPC分类号： C22B34/14 ,  G21C3/06 ,  C22B9/22

    CPC分类号： G21C3/07 ,  C22B9/228 ,  C22B34/14 ,  G21Y2002/103 ,  G21Y2002/201 ,  G21Y2002/206 ,  G21Y2004/40 ,  Y02E30/40 ,  Y10T29/49929 ,  Y10T29/49988 ,  Y10T29/49991

    摘要： A method pf producing a composite nuclear fuel cladding lined with a liner of high purity zirconium charaterized in that a raw material of zirconium sponge disposed in a hearth cavity is irradiated with an electron beam while controlling an amount of heat per a unit volume (Ws/mm³) according to an oxygen removal rate of the raw material determined by oxygen concentration of the raw material and a target oxygen concentration of an ingot for a liner to be refined, and zircaloy cladding is lined with the liner. The hearth cavity has a preferable shape in which the ratio of the cavity surface to the cavity volume is 0.20mm⁻¹ or larger.

    摘要翻译： 一种生产复合核燃料包覆层的方法，其中衬有高纯度锆的衬垫，其特征在于，设置在炉膛腔中的锆海绵的原料用电子束照射，同时控制每单位体积的热量（Ws / 根据由原料的氧浓度确定的原料的氧除去率和待精制衬管的锭的目标氧浓度，并且氧化锆包覆层与衬垫衬里，根据氧气除去率。 炉膛腔具有其中空腔表面与空腔体积的比率为0.20mm <1>或更大的优选形状。

    Composite member and fuel assembly using the same
    5.
    发明公开
    Composite member and fuel assembly using the same 审中-公开
    Schichtkörperund Brennstoffkassette mit diesemSchichtkörper

    公开(公告)号：EP0937575A1

    公开(公告)日：1999-08-25

    申请号：EP99301038.8

    申请日：1999-02-12

    申请人： HITACHI, LTD.

    发明人： Fujieda, Tadashi ,  Tomida, Kazuo ,  Inagaki, Masahisa ,  Nakajima, Junjiro ,  Ito, Kenichi

    IPC分类号： B32B15/01 ,  C22C16/00 ,  G21C7/04 ,  G21C3/324

    CPC分类号： B32B15/01 ,  C22C16/00 ,  C22C28/00 ,  G21C3/324 ,  G21C3/326 ,  G21C7/04 ,  G21Y2002/103 ,  G21Y2002/303 ,  G21Y2004/10 ,  G21Y2004/30 ,  Y02E30/38 ,  Y02E30/39

    摘要： Disclosed are a composite member capable of suitably suppressing the excess reactivity without addition of a neutron absorbing material or burnable poison in fuel rods by use of a Zr-Gd alloy improved in characteristics of pure Gd as the neutron absorbing material, and a fuel assembly, cladding tube, spacer, water rod, channel box, and control rod using the composite member. In particular, disclosed is a fuel assembly in which at least one of a cladding tube, spacer, water rod, channel box, and control rod employs a composite member which is composed of a member made from a Zr-Gd alloy containing 20 wt% or more of Gd and a member made from a Zr alloy higher in corrosion resistance than the Zr-Gd alloy, wherein the member made from the Zr-Gd alloy is incorporated in the member made from the Zr alloy.

    摘要翻译： 公开了能够通过使用改善了作为中子吸收材料的纯Gd特性的Zr-Gd合金，在燃料棒中不添加中子吸收材料或燃烧毒物的情况下适当地抑制过量反应性的复合构件，以及燃料组件， 包层管，间隔件，水杆，通道箱和使用复合构件的控制杆。 特别地，公开了一种燃料组件，其中包层管，间隔件，水杆，通道箱和控制杆中的至少一个采用复合构件，该复合构件由包含20重量％的Zr-Gd合金制成的构件组成， 以上的Gd和由Zr-Gd合金的耐腐蚀性较高的Zr合金制成的部件，其中由Zr-Gd合金制成的部件结合在由Zr合金制成的部件中。

    Zirconium-based alloy with high corrosion resistance
    7.
    发明公开
    Zirconium-based alloy with high corrosion resistance 失效
    高耐腐蚀性的锆合金。

    公开(公告)号：EP0227989A1

    公开(公告)日：1987-07-08

    申请号：EP86117134.6

    申请日：1986-12-09

    申请人： HITACHI, LTD.

    发明人： Inagaki, Masahisa ,  Takase, Iwao ,  Kanno, Masayoshi ,  Kuniya, Jiro ,  Akahori, Kimihiko ,  Masaoka, Isao ,  Maki, Hideo ,  Nakajima, Junjiro

    IPC分类号： C22C16/00 ,  C22F1/18

    CPC分类号： C22F1/186 ,  C22C16/00

    摘要： A zirconium-based alloy with a high corrosion resistance, consisting essentially of 1 to 2wt% Sn, 0.20 to 0.35wt% Fe, 0.03 to 0.16wt% Ni and the balance substantially Zr. The Fe/Ni content ratio of the alloy ranges between 1.4 and 8. The structure of the alloy has a fine intermetallic compound of Sn and Ni precipitated within the zirconium crystal grain of a-phase. The alloy may further contain 0.05 to 0.15wt% Cr. This alloy exhibits reduced hydrogen absorption rate and suffers from no nodular corrosion, so that it can suitably be used as a material of nuclear fuel cladding tubes (1). The nuclear fuel cladding tube (1) made of this alloy exhibits extended service life when used in a nuclear reactor of high degree of burn-up.