Soft Magnetic Powders and Compacts
    31.
    发明申请
    Soft Magnetic Powders and Compacts 审中-公开
    软磁粉和压块

    公开(公告)号:US20090295518A1

    公开(公告)日:2009-12-03

    申请号:US12473982

    申请日:2009-05-28

    摘要: A water atomized Fe powder for a magnetic compact reduced in deformation resistance during molding and annealing temperature for removing strains is provided. A compact having improved magnetic properties is also provided. The water atomized powder containing at least one element selected from Nb, Ta, Ti, Zr and V in an amount of 0.001-0.03 atom % is soft magnetic and has a precipitation in the matrix, which is composed of at least one element selected from Nb, Ta, Ti, Zr and V and oxygen as a main component and has an average size of 0.02-0.5 μm. Disclosed is a method for manufacturing a soft magnetic powder includes adding at least one element selected from Nb, Ta, Ti, Zr and V, and annealing in a hydrogen-containing reduction atmosphere. This method decrease gaseous impurities, particularly oxygen, and defuse it, to improve the magnetic properties of the powder and compact.

    摘要翻译: 提供了一种用于磁性结合体的水雾化Fe粉末,在模制期间降低了变形阻力,并且提供了用于去除应变的退火温度。 还提供了具有改善的磁性能的压块。 含有0.001-0.03原子%的选自Nb,Ta,Ti,Zr和V中的至少一种元素的水雾化粉末是软磁性的,并且在基体中具有沉淀,该沉淀物由至少一种选自 Nb,Ta,Ti,Zr和V,氧为主要成分,平均粒径为0.02-0.5μm。 公开了一种制造软磁性粉末的方法,包括添加至少一种选自Nb,Ta,Ti,Zr和V的元素,并在含氢还原气氛中进行退火。 该方法减少了气体杂质,特别是氧气,并使其易于除去,从而提高了粉末的磁性能和致密性。

    A nuclear reactor comprising a reactor vessel and structural members
made of an austenitic stainless steel having superior resistance to
irradiation-induced segregation
    34.
    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

    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。