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12 条记录 (耗时 0.022 秒)

    Feedwater heater
    1.
    发明授权
    Feedwater heater 失效
    给水加热器

    公开(公告)号：US4461346A

    公开(公告)日：1984-07-24

    申请号：US306234

    申请日：1981-09-28

    申请人： Yoshiyuki Hoshino ,  Shyuichi Imazu ,  Masahiko Miyai ,  Yoshikuni Oshima ,  Masakiyo Izumiya

    发明人： Yoshiyuki Hoshino ,  Shyuichi Imazu ,  Masahiko Miyai ,  Yoshikuni Oshima ,  Masakiyo Izumiya

    IPC分类号： F22D1/32 ,  F28B9/10 ,  F28D7/06 ,  F28F9/02 ,  F28F9/22

    CPC分类号： F28D7/06 ,  F22D1/32 ,  F28B9/10 ,  F28F9/0202 ,  Y10S165/211

    摘要： A horizontal feedwater heater for use in heat power stations, of the type having a shell, a plurality of U-bent heat transfer tubes extended in the longitudinal direction of the shell and a vent tube extended in the longitudinal direction of the shell substantially at the center of the latter and adapted for extracting and discharging non-condensed gas. The feedwater heater has a baffle disposed at each side of the vent tube and having a horizontal plate portion extended horizontally from the vent tube and an inclined plate portion inclined downwardly from the end of the horizontal plate portion at an obtuse angle to the latter. The length of projection of the baffle from the vent tube is varied along the length of the shell in accordance with the ratio of amount of heat exchanged between the steam and feedwater in each axial section of the tube nest connected to the water inlet to the amount of heat exchanged between these fluids in the corresponding tube nest section of the feedwater outlet side, thereby to permit an efficient extraction of the non-condensed gas. The structural members connectable with the heating steam is made from a low alloy steel containing more than 1% of Cr to exhibit a high corrosion resistance.

    摘要翻译： 一种用于热发电站的水平给水加热器，具有壳体的类型，沿壳体的纵向方向延伸的多个U形弯曲的传热管，以及沿壳体的纵向方向延伸的通风管， 后者的中心，适用于提取和排出非冷凝气体。 给水加热器具有设置在通气管的每一侧的挡板，具有从通气管水平延伸的水平板部分和从水平板部分的端部向下倾斜向下倾斜的倾斜板部分。 挡板从排气管突出的长度随壳体长度而变化，这是根据连接到进水口的管巢的每个轴向部分中的蒸汽和给水之间交换的热量之比， 在给水出口侧的相应管座部分中的这些流体之间换热的热量，从而有效地提取非冷凝气体。 与加热蒸汽连接的结构部件由含有1％以上Cr的低合金钢制成，具有高耐腐蚀性。

    Nuclear power plant providing a function of suppressing the deposition of radioactive substance
    5.
    发明授权
    Nuclear power plant providing a function of suppressing the deposition of radioactive substance 失效
    提供抑制放射性物质沉积功能的核电站

    公开(公告)号：US4722823A

    公开(公告)日：1988-02-02

    申请号：US525889

    申请日：1983-08-24

    申请人： Takashi Honda ,  Toshio Kawakami ,  Masakiyo Izumiya ,  Akira Minato ,  Katsumi Ohsumi

    发明人： Takashi Honda ,  Toshio Kawakami ,  Masakiyo Izumiya ,  Akira Minato ,  Katsumi Ohsumi

    IPC分类号： G21D1/00 ,  G21C13/087 ,  G21C13/10 ,  G21F9/00 ,  G21C11/00

    CPC分类号： G21C13/087 ,  G21C13/10 ,  Y02E30/40

    摘要： A nuclear power plant using a structural material consisting of metal which comes into contact with a liquid in which radioactive substances are dissolved has a function to suppress the deposition of the radioactive substances. In this function, metal elements constituting the surface layer of the structural material which comes into contact with the liquid are oxidized by injecting oxidizing agents from outside, thereby preliminarily producing an oxide film. The oxidizing agents comprise at least one kind selected from the group consisting of oxygen, hydrogen peroxide, chromate, nitrite, molybdate, tungstate and ferrate. Particularly, by suppressing the deposition of radioactive substances on a stainless steel, the dose rate of exposure of workers is effectively reduced.

    摘要翻译： 使用与溶解有放射性物质的液体接触的金属构成的结构材料的核电站具有抑制放射性物质沉积的功能。 在该功能中，构成与液体接触的结构材料的表面层的金属元素通过从外部注入氧化剂而被氧化，从而预先生成氧化膜。 氧化剂包括选自氧，过氧化氢，铬酸盐，亚硝酸盐，钼酸盐，钨酸盐和高铁酸盐中的至少一种。 特别是通过抑制放射性物质在不锈钢上的沉积，有效地降低了工作人员的接触剂量。

    A nuclear reactor comprising a reactor vessel and structural members made of an austenitic stainless steel having superior resistance to irradiation-induced segregation
    6.
    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。