Effects of silicon, carbon and molybdenum additions on IASCC of neutron irradiated austenitic stainless steels

被引:9
|
作者
Nakano, J [1 ]
Miwa, Y [1 ]
Kohya, T [1 ]
Tsukada, T [1 ]
机构
[1] Japan Atom Energy Res Inst, Tokai Res Estab, Tokai, Ibaraki 3191195, Japan
关键词
D O I
10.1016/j.jnucmat.2004.04.098
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
To study the effects of minor elements on irradiation assisted stress corrosion cracking (IASCC), high purity type 304 and 316 stainless steels (SSs) were fabricated and minor elements, Si or C were added. After neutron irradiation to 3.5 x 10(25) n/m(2) (E > 1 MeV), slow strain rate tests (SSRTs) of irradiated specimens were conducted in oxygenated high purity water at 561 K. Specimen fractured surfaces were examined using a scanning electron microscope (SEM) after the SSRTs. The fraction of intergranular stress corrosion cracking (IGSCC) on the fractured surface after the SSRTs increased with neutron fluence. In high purity SS with added C, the fraction of IGSCC was the smallest in the all SSs, although irradiation hardening level was the largest of all the SSs. Addition of C suppressed the susceptibility to IGSCC. (C) 2004 Elsevier B.V. All rights reserved.
引用
下载
收藏
页码:643 / 647
页数:5
相关论文
共 50 条
  • [41] The silicon alloying thermodynamics in the austenitic stainless steels
    Brandusa, Ghiban
    Nicolae, Ghiban
    Nicolae, Serban
    Augustin, Semenescu
    METALURGIA INTERNATIONAL, 2008, 13 (11): : 5 - 12
  • [42] IASCC Initiation in Highly Irradiated Stainless Steels under Uniaxial Constant Load Conditions
    Nishioka, Hiromasa
    Fukuya, Koji
    Fujii, Katsuhiko
    Torimaru, Tadahiko
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2008, 45 (10) : 1072 - 1077
  • [43] IASCC susceptibility and slow tensile properties of highly-irradiated 316 stainless steels
    Fukuya, K
    Nakano, M
    Fujii, K
    Torimaru, T
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2004, 41 (06) : 673 - 681
  • [44] TITANIUM CARBIDE DISTRIBUTION IN NEUTRON-IRRADIATED, RAPIDLY SOLIDIFIED AUSTENITIC STAINLESS-STEELS OF VARYING TITANIUM AND CARBON CONTENT
    IMESON, D
    TONG, CH
    VANDERSANDE, JB
    HARLING, OK
    JOURNAL OF METALS, 1982, 34 (08): : 58 - 59
  • [45] Pitting corrosion behaviour of austenitic stainless steels - combining effects of Mn and Mo additions
    Pardo, A.
    Merino, M. C.
    Coy, A. E.
    Viejo, F.
    Arrabal, R.
    Matykina, E.
    CORROSION SCIENCE, 2008, 50 (06) : 1796 - 1806
  • [46] A review of irradiation effects on LWR core internal materials - IASCC susceptibility and crack growth rates of austenitic stainless steels
    Chopra, O. K.
    Rao, A. S.
    JOURNAL OF NUCLEAR MATERIALS, 2011, 409 (03) : 235 - 256
  • [47] Effects of minor elements on IASCC of type 316 model stainless steels
    Tsukada, T
    Miwa, Y
    Nakajima, H
    Kondo, T
    PROCEEDINGS OF THE EIGHTH INTERNATIONAL SYMPOSIUM ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS - WATER REACTORS, VOLS 1 AND 2, 1997, : 795 - 802
  • [48] Effects of low temperature neutron irradiation on deformation behavior of austenitic stainless steels
    Pawel, JE
    Rowcliffe, AF
    Alexander, DJ
    Grossbeck, ML
    Shiba, K
    JOURNAL OF NUCLEAR MATERIALS, 1996, 233 : 202 - 206
  • [49] EFFECTS OF NITROGEN AND CARBON ON VOID SWELLING IN AUSTENITIC STAINLESS-STEELS
    IGATA, N
    KOHNO, Y
    TANABE, N
    ROTMAN, F
    TSUNAKAWA, H
    JOURNAL OF NUCLEAR MATERIALS, 1984, 122 (1-3) : 219 - 223
  • [50] Effect of Molybdenum on the Corrosion Resistance of Austenitic Stainless Steels.
    Defranoux, J.M.
    Materials Technology, 1974, 62 (03) : 137 - 143