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
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页码:147 / 154
页数:8
相关论文
共 36 条
  • [1] MYRRHA: A multipurpose accelerator driven system for research & development
    Abderrahim, HA
    Kupschus, P
    Malambu, E
    Benoit, P
    Van Tichelen, K
    Arien, B
    Vermeersch, F
    D'hondt, P
    Jongen, Y
    Ternier, S
    Vandeplassche, D
    [J]. NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT, 2001, 463 (03) : 487 - 494
  • [2] ARAKAWA K, 1988, J NUCL MATER, V329, P1232
  • [3] BOZORTH RM, 1951, CRC HDB ELECT RESIST
  • [4] DIETER GE, 1986, MECH METAL
  • [5] DIMITROV C, 1991, ANN CHIM-SCI MAT, V16, P319
  • [6] Materials research towards a fusion reactor
    Ehrlich, K
    [J]. FUSION ENGINEERING AND DESIGN, 2001, 56-57 : 71 - 82
  • [7] Filippova NP, 2000, PHYS MET METALLOGR+, V90, P145
  • [8] Post-irradiation deformation in a Fe-9%Cr alloy
    Gelles, DS
    Schäublin, RE
    [J]. MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, 2001, 309 (309-310): : 82 - 86
  • [9] MICROSTRUCTURAL EXAMINATION OF NEUTRON-IRRADIATED SIMPLE FERRITIC ALLOYS
    GELLES, DS
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1982, 108 (1-2) : 515 - 526
  • [10] VOID SWELLING IN BINARY FE-CR ALLOYS AT 200 DPA
    GELLES, DS
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1995, 225 : 163 - 174