Effect of Cr on the mechanical properties and microstructure of Fe-Cr model alloys after n-irradiation

被引:138
|
作者
Madjasevic, M. [1 ]
Alrriazouzi, A. [1 ]
机构
[1] CEN SCK, Nucl Mat Sci Inst, B-2400 Mol, Belgium
关键词
D O I
10.1016/j.jnucmat.2008.02.061
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
High-chromium ferritic-martensitic steels are candidate structural materials for high-temperature applications in fusion reactors and accelerator driven systems (ADS). Cr concentration has been shown to be a key parameter which needs to be optimized in order to guarantee the best corrosion and swelling resistance, together with the minimum embrittlement. The behavior of Fe-Cr model alloys with different Cr concentrations (0, 2.5, 5, 9 and 12 wt%Cr) has been studied. Tensile tests have been performed in order to characterize the flow properties in the temperature range from -160 degrees C to 300 degrees C. The trend of the yield strength with temperature shows that the strain hardening is the same for all materials at low temperatures, even though they have different microstructures. The same materials have been neutron-irradiated at 300 degrees C in the BR2 reactor of SCK.CEN, up to three different doses (0.06, 0.6 and 1.5 dpa). The results obtained so far indicate that even at these low doses, the Cr content affects the hardening behavior of Fe-Cr binary alloys. Using the Orowan mechanism, the TEM observed microstructure provides an explanation of the obtained hardening but only at the very low dose, 0.06 dpa. At higher doses, other hardening mechanisms are needed. (c) 2008 Elsevier B.V. All rights reserved.
引用
收藏
页码:147 / 154
页数:8
相关论文
共 50 条
  • [1] IRRADIATION HARDENING OF FE-CR ALLOYS
    SUGANUMA, K
    KAYANO, H
    JOURNAL OF NUCLEAR MATERIALS, 1983, 118 (2-3) : 234 - 241
  • [2] Graded microstructure and mechanical properties of spark plasma sintered Fe-Cr alloys
    Zhang, Xinchang
    Wang, Qiang
    Kane, Joshua J.
    Rufner, Jorgen F.
    Sun, Cheng
    JOURNAL OF ALLOYS AND COMPOUNDS, 2023, 967
  • [3] MECHANICAL-PROPERTIES CHANGES OF FE-CR ALLOYS BY FAST-NEUTRON IRRADIATION
    SUGANUMA, K
    KAYANO, H
    YAJIMA, S
    JOURNAL OF NUCLEAR MATERIALS, 1982, 105 (01) : 23 - 35
  • [4] Effect of microstructure on the wear resistance of borided Fe-Cr alloys
    Dybkov, Vasyl I.
    INTERNATIONAL JOURNAL OF MATERIALS RESEARCH, 2013, 104 (07) : 617 - 629
  • [5] MECHANICAL-PROPERTIES OF SPINODALLY DECOMPOSED FE-CR AND FE-CR-MO ALLOYS
    PARK, K
    SCHWARTZ, LH
    JOURNAL OF METALS, 1983, 35 (08): : A49 - A49
  • [6] Investigation of Cr-atom clustering in Fe-Cr model alloys under irradiation
    Kwon, J.
    Lee, Y-B
    Jin, H-H
    Shin, C.
    Lee, G-G
    RADIATION EFFECTS AND DEFECTS IN SOLIDS, 2014, 169 (05): : 467 - 477
  • [7] Effect of Cr on the microstructure and mechanical properties of Cu-20vol%(Fe-Cr) in situ composites
    Sun, Shi-Qing
    Mao, Lei
    Liu, Zong-Mao
    Guo, Zhi-Meng
    Yin, Sheng
    Cailiao Rechuli Xuebao/Transactions of Materials and Heat Treatment, 2003, 24 (01):
  • [8] Effect of spinodal decomposition on the mechanical behavior of Fe-Cr alloys
    Soriano-Vargas, Orlando
    Avila-Davila, Erika O.
    Lopez-Hirata, Victor M.
    Cayetano-Castro, Nicolas
    Gonzalez-Velazquez, Jorge L.
    MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, 2010, 527 (12): : 2910 - 2914
  • [9] Swelling and microstructure of pure Fe and Fe-Cr alloys after neutron irradiation to ∼26 dpa at 400 °C
    Konobeev, Yu. V.
    Dvoriashin, A. M.
    Porollo, S. I.
    Garner, F. A.
    JOURNAL OF NUCLEAR MATERIALS, 2006, 355 (1-3) : 124 - 130
  • [10] The microstructure and tensile properties of Fe-Cr alloys after neutron irradiation at 400°C to 5.5-7.1 dpa
    Porollo, SI
    Dvoriashin, AM
    Vorobyev, AN
    Konobeev, YV
    JOURNAL OF NUCLEAR MATERIALS, 1998, 256 (2-3) : 247 - 253