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    Zirconium alloy having superior corrosion resistance
    1.
    发明授权
    Zirconium alloy having superior corrosion resistance 失效
    锆合金具有优良的耐腐蚀性

    公开(公告)号：US4664727A

    公开(公告)日：1987-05-12

    申请号：US506393

    申请日：1983-06-21

    申请人： Masahisa Inagaki ,  Ryutaro Jinbo ,  Keiichi Kuniya ,  Isao Masaoka ,  Hideo Maki

    发明人： Masahisa Inagaki ,  Ryutaro Jinbo ,  Keiichi Kuniya ,  Isao Masaoka ,  Hideo Maki

    IPC分类号： C22C16/00 ,  C22F1/18

    CPC分类号： C22F1/186

    摘要： A zirconium alloy having superior corrosion resistance, containing Sn of a small amount not less than the amount of Sn existing in the solid-solution of the zirconium alloy at a room temperature, and at least one kind of Fe and Cr each of a small amount not less than the amount of each of Fe and Cr existing in the solid-solution of the zirconium alloy at a room temperature,the zirconium alloy being annealed after the solution heat treatment at a temperature at which both the .alpha. phase and .beta. phase thereof are included in the zirconium alloy,the total amount of said at least one kind of Fe and Cr existing in the solid-solution of the zirconium alloy being not less than 0.26%.

    摘要翻译： 具有优异的耐腐蚀性的锆合金，其含有少量不小于室温下的锆合金的固溶体中的Sn的量的Sn和至少一种少量的Fe和Cr 不少于在室温下锆合金固溶体中存在的Fe和Cr中的每一种，锆合金在固溶热处理后在其α相和β相均为 包含在锆合金中，锆合金固溶体中存在的所述至少一种Fe和Cr的总量不小于0.26％。

    Zirconium-based alloy with high corrosion resistance
    4.
    发明授权
    Zirconium-based alloy with high corrosion resistance 失效
    锆基合金具有高耐腐蚀性

    公开(公告)号：US4810461A

    公开(公告)日：1989-03-07

    申请号：US940723

    申请日：1986-12-09

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

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

    IPC分类号： G21C3/07 ,  C22C16/00 ,  C22F1/00 ,  C22F1/18 ,  G21C3/06

    CPC分类号： C22F1/186 ,  C22C16/00

    摘要： A zirconium-based alloy with a high corrosion resistance, consisting essentially of 1 to 2 wt % Sn, 0.20 to 0.35 wt % Fe, 0.03 to 0.16 wt % 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 fine intermetallic compound of Sn and Ni is precipitated within the zirconium crystal grain of .alpha.-phase. The alloy may further contain 0.05 to 0.15 wt % 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. The nuclear fuel cladding tube made of this alloys exhibits extended service life when used in a nuclear reactor of high degree of burn-up.

    摘要翻译： 具有高耐腐蚀性的锆基合金基本上由Sn组成为1〜2重量％，Fe为0.20〜0.35重量％，Ni为0.03〜0.16重量％，余量基本为Zr。 合金的Fe / Ni含量比在1.4和8之间。合金的结构具有细小的Sn的金属间化合物，Ni在α相的锆晶粒内析出。 该合金还可以含有0.05〜0.15重量％的Cr。 该合金显示出降低的氢吸收率，并且没有结节腐蚀，因此它可以适当地用作核燃料包覆管的材料。 由这种合金制成的核燃料包层管在高度燃烧的核反应堆中使用时，寿命延长。

    Method of cooling weld in steel piping and apparatus therefor
    7.
    发明授权
    Method of cooling weld in steel piping and apparatus therefor 失效
    钢管道焊接冷却方法及其设备

    公开(公告)号：US4223197A

    公开(公告)日：1980-09-16

    申请号：US897403

    申请日：1978-04-18

    申请人： Katsuyuki Imai ,  Isao Masaoka ,  Yositeru Chiba ,  Jiro Kuniya

    发明人： Katsuyuki Imai ,  Isao Masaoka ,  Yositeru Chiba ,  Jiro Kuniya

    IPC分类号： B23K9/028 ,  B23K37/00 ,  B23K31/06

    CPC分类号： B23K9/0282 ,  B23K37/003

    摘要： A method for cooling a weld in steel piping during butt welding with cooling of the inside comprises, after joining of pipe ends by a root pass on the inside, cooling the junction being welded by subsequent passes with injection of a liquid medium at room temperature from the center of the pipe against the surrounding wall, in a direction between radial and tangential directions relative to the inner pipe surface. An apparatus for practicing the cooling method comprises a rotatable multi-nozzle assembly having a radius of rotation corresponding to the inside diameter of the pipe and is capable of injecting the cooling medium against the inner surface of the pipe, a duct for conducting the cooling medium to the nozzles, and a pumping device for forcing the cooling medium under pressure into the nozzles.

    摘要翻译： 在内部冷却的对接焊接期间冷却钢管道中的焊接的方法包括：在管端部通过内侧的根部接合之后，通过随后的通过在室温下注入液体介质来冷却被焊接的接合部 管道的中心相对于内管表面在径向和切向之间的方向上相对于周围壁。 用于实施冷却方法的装置包括具有与管的内径相对应的旋转半径的可旋转多喷嘴组件，并且能够将冷却介质喷射到管的内表面上，用于传导冷却介质 以及用于迫使冷却介质在压力下进入喷嘴的泵送装置。

    A nuclear reactor comprising a reactor vessel and structural members made of an austenitic stainless steel having superior resistance to irradiation-induced segregation
    8.
    发明授权
    A nuclear reactor comprising a reactor vessel and structural members made of an austenitic stainless steel having superior resistance to irradiation-induced segregation 失效
    一种包括反应器容器和由奥氏体不锈钢制成的结构构件的核反应堆具有优异的抗辐照诱导偏析性

    公开(公告)号：US5316597A

    公开(公告)日：1994-05-31

    申请号：US936647

    申请日：1992-08-28

    申请人： Takahiko Kato ,  Shinzo Ikeda ,  Yasuhisa Aono ,  Masakiyo Izumiya ,  Kiyotomo Nakata ,  Isao Masaoka ,  Heishichiro Takahashi

    发明人： Takahiko Kato ,  Shinzo Ikeda ,  Yasuhisa Aono ,  Masakiyo Izumiya ,  Kiyotomo Nakata ,  Isao Masaoka ,  Heishichiro Takahashi

    IPC分类号： C22C38/00 ,  C22C38/40 ,  C22C38/46 ,  C22C38/48 ,  C22C38/50 ,  G21B1/11 ,  G21B1/17 ,  G21C5/00

    CPC分类号： C22C38/50 ,  C22C38/40 ,  C22C38/46 ,  C22C38/48 ,  Y10S376/90

    摘要： A nuclear reactor having structural members made of austenitic stainless steel which is corrosion-resistant in an environment of neutron irradiation, and can suppress stress corrosion cracking and embrittlement. At least one additive selected from the group consisting of Ti more than 0.2% by weight but not more than 0.6%, Zr more than 0.2% but not more than 1.14%, Hf more than 0.2% but not more than 2.24%, V more than 0.2% but not more than 0.64%, Nb more than 0.5% but not more than 1.17% and Ta more than 0.5% but not more than 2.27% is added to austenitic stainless steel containing Cr, Ni and so on, and said at least one exists in a solid-solution state. In addition, the steel has a wholly austenitic structure substantially free of carbide. In order to maintain the irradiation-induced segregation prevention effected by the addition element, the C content is limited to 0.01 to 0.008%, and the N content is limited to 0.001 to 0.0%. The irradiation-induced segregation, of the constituent elements, such as Cr and Ni, occurring in a grain boundary under irradiation, can be prevented, and the deterioration of the corrosion resistance of the material, as well as the embrittlement, can be prevented.

    摘要翻译： 具有由奥氏体不锈钢制成的结构构件的核反应堆，其在中子照射环境中耐腐蚀，并且可以抑制应力腐蚀开裂和脆化。 至少一种添加剂选自Ti大于0.2重量％但不大于0.6重量％，Zr大于0.2重量％但不大于1.14重量％，Hf大于0.2重量％但不大于2.24重量％，V多 超过0.2％但不超过0.64％，Nb超过0.5％但不超过1.17％，Ta含量超过0.5％但不超过2.27％，则含有Cr，Ni等奥氏体不锈钢， 在固溶状态下最少存在。 此外，钢具有基本上不含碳化物的完全奥氏体结构。 为了保持由添加元素进行的照射诱导的偏析防止，C含量限于0.01〜0.008％，N含量限定在0.001〜0.0％。 可以防止在照射下的晶界中发生的诸如Cr和Ni的组成元素的照射诱导的偏析，并且可以防止材料的耐腐蚀性劣化以及脆化。

    Method of producing a cladding tube for reactor fuel
    9.
    发明授权
    Method of producing a cladding tube for reactor fuel 失效
    生产反应堆燃料包层管的方法

    公开(公告)号：US4718949A

    公开(公告)日：1988-01-12

    申请号：US915555

    申请日：1986-10-06

    申请人： Iwao Takase ,  Toshimi Yoshida ,  Shinzo Ikeda ,  Isao Masaoka ,  Junjiro Nakajima

    发明人： Iwao Takase ,  Toshimi Yoshida ,  Shinzo Ikeda ,  Isao Masaoka ,  Junjiro Nakajima

    IPC分类号： C22C16/00 ,  C22F1/18 ,  G21C3/06 ,  G21C3/07

    CPC分类号： G21C3/07 ,  Y02E30/40 ,  Y10S376/90

    摘要： A method of producing cladding tube comprises a step of temperature-gradient annealing in which the inner surface of the tube is heated to a temperature higher than the recrystallization temperature thereof, while the outer surface of the tube is cooled, after the tube has been hot-extruded. The temperature-gradient annealing is effected while a temperature gradient is maintained between the inner surface and the outer surface of the cladding tube. While keeping the inner surface at a temperature higher than the recrystallization temperature, and the outer surface at a temperature lower than the recrystallization temperature. The cladding tube is obtained with the outer surface which has an excellent resistance to nodular corrosion and a soft inner surface which has an excellent resistance to stress corrosion cracking.

    摘要翻译： 制造包层管的方法包括将管的内表面加热到高于其再结晶温度的温度的温度梯度退火步骤，同时管的外表面被冷却后，管被热 - 挤压。 在包覆管的内表面和外表面之间保持温度梯度的同时进行温度梯度退火。 同时将内表面保持在比再结晶温度高的温度，而外表面在低于再结晶温度的温度下。 获得具有优异的抗结块腐蚀性的外表面和具有优异的耐应力腐蚀开裂性的软内表面的包覆管。

    Method of making a structure immune against stress corrosion cracking
    10.
    发明授权
    Method of making a structure immune against stress corrosion cracking 失效
    使结构免受应力腐蚀开裂的方法

    公开(公告)号：US4234119A

    公开(公告)日：1980-11-18

    申请号：US933555

    申请日：1978-08-14

    申请人： Isao Masaoka ,  Katsuyuki Imai

    发明人： Isao Masaoka ,  Katsuyuki Imai

    IPC分类号： B23K33/00 ,  B23K9/02 ,  B23K9/04 ,  B23K31/02

    CPC分类号： B23K9/0216 ,  B23K9/048

    摘要： A groove is provided on the side of a metallic structure opposite to the side thereof which is exposed to a corrosive atmosphere, and the groove is subjected to build-up welding while cooling with a liquid coolant, whereby any stress corrosion cracking which otherwise occurs on the side of the structure to be exposed to the corrosive atmosphere can be prevented. Especially, this method of manufacture is appropriate for the repair welding of a butt-welded pipe of austenite type stainless steel, and it is effective to perfectly prevent the stress corrosion cracking of the pipe prone to be caused by reactor water during use in a nuclear reactor.

    摘要翻译： 在暴露于腐蚀性气氛的与金属结构体相反侧的金属结构侧设置有槽，并且在冷却液体的同时对槽进行堆积焊接，否则发生任何应力腐蚀开裂 可以防止暴露于腐蚀性气氛的结构的一侧。 特别是，这种制造方法适用于奥氏体型不锈钢对接焊管的修补焊接，并且有效地完全防止在核中使用时容易引起反应堆水的管道的应力腐蚀开裂 反应堆。