The microstructure and associated tensile properties of irradiated fcc and bcc metals

被引:306
作者
Victoria, M [1 ]
Baluc, N
Bailat, C
Dai, Y
Luppo, MI
Schaublin, R
Singh, BN
机构
[1] PSI, CRPP Fus Technol Mat, EPFL, CH-5232 Villigen, Switzerland
[2] Paul Scherrer Inst, CH-5232 Villigen, Switzerland
[3] Riso Natl Lab, Dept Mat Res, DK-4000 Roskilde, Denmark
关键词
D O I
10.1016/S0022-3115(99)00203-2
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The differences and similarities of behaviour between fee and bcc metals after irradiation have been investigated. For this purpose, fee Cu, Pd and 304 stainless steel and bcc Fe, Mo and Mo-5% Re were irradiated with either neutrons or 590 MeV protons at temperatures below recovery stage V. It is shown that a dense population of defect clusters (up to 10(22)-10(24) m(-3)) develops, the type of cluster formed depending apparently on the stacking fault energy. In the case of stacking fault tetrahedra formed in Cu, their size is independent of dose, while interstitial loops in stainless steel grow at neutron doses higher than 1 dpa. The defect microstructure is found to be independent of the recoil energy spectra in this temperature region, but shows a very strong dependence on the type of crystalline structure. The results of tensile testing indicate the presence of radiation hardening, starting at very low doses as an upper yield point develops followed by a (serrated) yield region. The main deformation mode observed is dislocation channeling. The hardening is modelled in terms of the initial dislocation locking by the irradiation-induced defects followed by the dispersed hardening induced by the global distribution of clusters in the matrix. (C) 2000 Published by Elsevier Science B.V. All rights reserved.
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页码:114 / 122
页数:9
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