TY - JOUR
T1 - Modeling tensile response and flow localization effects in selected copper alloys
AU - Pan, Xiao
AU - Wu, Xianglin
AU - Li, Meimei
AU - Stubbins, J. F.
N1 - Funding Information:
The work was supported by the US Department of Energy under grant DE-FG07-02D14337. The authors would also like thank Dr Edwards, PNNL for sharing Cu tensile data and Drs Farrell, Byun, and Hashimoto, ORNL for sharing 316SS tensile data.
PY - 2004/8/1
Y1 - 2004/8/1
N2 - Radiation-induced defect structures are known to elevate material yield strength and reduce material ductility. Together, these changes substantially reduce uniform elongation compared to the unirradiated material condition so that the small strains induce plastic instability. This process, commonly known as flow localization, is examined here for selected copper alloys and compared to similar response in 316SS. It is found that uniform elongation levels are limited by a critical material strength which is independent of the irradiation damage state. This result establishes that the details of the post-yield flow and strain hardening processes are less important than the critical stress for controlling plastic instability. In the case of OFHC Cu, post-irradiation heat treatment restores some initial ductility, but also reduces the critical stress for incipient flow localization.
AB - Radiation-induced defect structures are known to elevate material yield strength and reduce material ductility. Together, these changes substantially reduce uniform elongation compared to the unirradiated material condition so that the small strains induce plastic instability. This process, commonly known as flow localization, is examined here for selected copper alloys and compared to similar response in 316SS. It is found that uniform elongation levels are limited by a critical material strength which is independent of the irradiation damage state. This result establishes that the details of the post-yield flow and strain hardening processes are less important than the critical stress for controlling plastic instability. In the case of OFHC Cu, post-irradiation heat treatment restores some initial ductility, but also reduces the critical stress for incipient flow localization.
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U2 - 10.1016/j.jnucmat.2004.04.027
DO - 10.1016/j.jnucmat.2004.04.027
M3 - Conference article
AN - SCOPUS:3342880193
SN - 0022-3115
VL - 329-333
SP - 1088
EP - 1092
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
IS - 1-3 PART B
T2 - Proceedings of the 11th Conference on Fusion Research
Y2 - 7 December 2003 through 12 December 2003
ER -