Effects of inclusions on fracture toughness of reduced-activation ferritic/martensitic F82H-IEA steels

被引:22
|
作者
Tanigawa, Hiroyasu [1 ]
Sawahata, Atsushi
Sokolov, Mikhail A.
Enomoto, Masato
Klueh, Ronald L.
Kohyama, Akira
机构
[1] Japan Atom Energy Agcy, Naka Fus Inst, Tokai, Ibaraki 3191195, Japan
[2] Ibaraki Univ, Mat Engn Div, Hitachi, Ibaraki 3168511, Japan
[3] Oak Ridge Natl Lab, Oak Ridge, TN 37831 USA
[4] Kyoto Univ, Inst Adv Energy, Uji, Kyoto 6110011, Japan
关键词
reduced-activation ferritic/martensitic steels; neutron irradiated; inclusion; Ta oxide; toughness; master curve;
D O I
10.2320/matertrans.48.570
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Reduced activation ferritic/martensitic steels (RAFs) are recognized as the primary candidate structural materials for fusion blanket systems. F82H is the RAF which has been developed and studied in Japan, and F82H-IEA heat, one of the world's first 5 ton heats of RAF, was provided and evaluated in various countries as a part of the IEA collaboration on fusion materials development. A problem with the steel is that some fracture toughness values obtained by IT type of compact tension (ITCT) specimens showed very low values in ductile brittle transition region. There might be several reasons for the scatter, and one of them could be related to the microstructural inhomogeneity of F82H-IEA. In the present study, this possibility was investigated focusing on inclusions formed in a plate of F82H-IEA steel by scanning (SEM) and transmission electron microscopy (TEM) equipped with EDS. The plates examined in this study were obtained from F82H-IEA heat no. 9753, nominally Fe-7.5Cr-2W-0.15V-0.02Ta-0.1C, in mass%. Analyses by SEM and TEM for the plates revealed that Ta does not form MX precipitates, but instead, it forms composite Al2O3 - Ta(V,Ti)O oxide, or single phase Ta(V)O oxide. The composite inclusions are rather dominant in the plate obtained from the bottom of the ingot, but not in the plate from the middle of the ingot. SEM observations also revealed that composite oxide tended to be observed at the crack-initiation site. These results suggest that the scatter of toughness values may be correlated with this microstructural inhomogeneity.
引用
收藏
页码:570 / 573
页数:4
相关论文
共 50 条
  • [11] Interfacial plasticity mediated by lath boundaries in reduced-activation ferritic/martensitic steels
    Ghaffarian, Hadi
    Na, Ye-Eun
    Jang, Dongchan
    JOURNAL OF NUCLEAR MATERIALS, 2022, 559
  • [12] Effect of Ta rich inclusions and microstructure change during precracking on bimodal fracture of reduced-activation ferritic/martensitic steels observed in transition range
    Tanigawa, Hiroyasu
    Sokolov, Mikhail A.
    Sawahata, Atsushi
    Hashimoto, Naoyuki
    Ando, Masami
    Shiba, Kiyoyuki
    Enomoto, Masato
    Klueh, Ronald L.
    Journal of ASTM International, 2009, 6 (05):
  • [13] Radiation induced phase instability of precipitates in reduced-activation ferritic/martensitic steels
    Tanigawa, H.
    Sakasegawa, H.
    Ogiwara, H.
    Kishimoto, H.
    Kohyama, A.
    JOURNAL OF NUCLEAR MATERIALS, 2007, 367 : 132 - 136
  • [14] Underwater explosive welding of tungsten to reduced-activation ferritic steel F82H
    Mori, Daichi
    Kasada, Ryuta
    Konishi, Satoshi
    Morizono, Yasuhiro
    Hokamoto, Kazuyuki
    FUSION ENGINEERING AND DESIGN, 2014, 89 (7-8) : 1086 - 1090
  • [15] Constitutive behavior and fracture toughness properties of the F82H ferritic/martensitic steel
    Spätig, P
    Odette, GR
    Donahue, E
    Lucas, GE
    JOURNAL OF NUCLEAR MATERIALS, 2000, 283 (PART I) : 721 - 726
  • [16] Specimen size effects on fracture toughness of JLF-1 reduced-activation ferritic steel
    Ono, H
    Kasada, R
    Kimura, A
    JOURNAL OF NUCLEAR MATERIALS, 2004, 329 : 1117 - 1121
  • [17] Stress corrosion cracking susceptibility of a reduced-activation martensitic steel F82H
    Miwa, Yukio
    Jitsukawa, Shiro
    Tsukada, Takashi
    JOURNAL OF NUCLEAR MATERIALS, 2009, 386-88 : 703 - 707
  • [18] Reduction method of DBTT shift due to irradiation for reduced-activation ferritic/martensitic steels
    Wakai, E.
    Okubo, N.
    Ando, M.
    Yamamoto, T.
    Takada, F.
    JOURNAL OF NUCLEAR MATERIALS, 2010, 398 (1-3) : 64 - 67
  • [19] Influence of helium on impact properties of reduced-activation ferritic/martensitic Cr-steels
    Forschungszentrum Karlsruhe, Institut für Materialforschung, P.O. Box 3640, D-76021 Karlsruhe, Germany
    不详
    J Nucl Mater, (450-454):
  • [20] Microstructure property analysis of HFIR-irradiated reduced-activation ferritic/martensitic steels
    Tanigawa, H
    Hashimoto, N
    Sakasegawa, H
    Klueh, RL
    Sokolov, MA
    Shiba, K
    Jitsukawa, S
    Kohyama, A
    JOURNAL OF NUCLEAR MATERIALS, 2004, 329 : 283 - 288