Ion irradiation induced defect evolution in Ni and Ni-based FCC equiatomic binary alloys

Jin, Ke; Zhang, Yanwen; Bei, Hongbin

doi:10.1016/j.jnucmat.2015.09.009

Ion irradiation induced defect evolution in Ni and Ni-based FCC equiatomic binary alloys

Journal Article · Wed Sep 09 00:00:00 EDT 2015 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2015.09.009· OSTI ID:1242668

Jin, Ke ^[1]; Zhang, Yanwen ^[1]; Bei, Hongbin ^[2]

Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Univ. of Tennessee, Knoxville, TN (United States)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

In order to explore the chemical effects on radiation response of alloys with multi-principal elements, defect evolution under Au ion irradiation was investigated in the elemental Ni, equiatomic NiCo and NiFe alloys. Single crystals were successfully grown in an optical floating zone furnace and their (100) surfaces were irradiated with 3 MeV Au ions at fluences ranging from 1 × 10¹³ to 5 × 10¹⁵ ions cm^–2 at room temperature. The irradiation-induced defect evolution was analyzed by using ion channeling technique. Experiment shows that NiFe is more irradiation-resistant than NiCo and pure Ni at low fluences. With continuously increasing the ion fluences, damage level is eventually saturated for all materials but at different dose levels. The saturation level in pure Ni appears at relatively lower irradiation fluence than the alloys, suggesting that damage accumulation slows down in the alloys. Here, under high-fluence irradiations, pure Ni has wider damage ranges than the alloys, indicating that defects in pure Ni have high mobility.

View Accepted Manuscript (DOE)

Research Organization:: Energy Frontier Research Centers (EFRC) (United States). Energy Dissipation to Defect Evolution (EDDE); Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Sponsoring Organization:: USDOE Office of Science (SC); USDOE Office of Science (SC), Basic Energy Sciences (BES)

Grant/Contract Number:: AC05-00OR22725

OSTI ID:: 1242668

Alternate ID(s):: OSTI ID: 22590286
OSTI ID: 1252043

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Vol. 471; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Effects of chemical alternation on damage accumulation in concentrated solid-solution alloys Ullah, Mohammad W.; Xue, Haizhou; Velisa, Gihan Scientific Reports, Vol. 7, Issue 1 https://doi.org/10.1038/s41598-017-04541-8	journal	June 2017
Direct Observation of Defect Range and Evolution in Ion-Irradiated Single Crystalline Ni and Ni Binary Alloys Lu, Chenyang; Jin, Ke; Béland, Laurent K. Scientific Reports, Vol. 6, Issue 1 https://doi.org/10.1038/srep19994	journal	February 2016
Delayed damage accumulation by athermal suppression of defect production in concentrated solid solution alloys Velişa, G.; Wendler, E.; Zhao, S. Materials Research Letters, Vol. 6, Issue 2 https://doi.org/10.1080/21663831.2017.1410863	journal	December 2017
Delayed damage accumulation by athermal suppression of defect production in concentrated solid solution alloys Velişa, G.; Wendler, E.; Zhao, S. Taylor & Francis https://doi.org/10.6084/m9.figshare.5711458	text	January 2017
Delayed damage accumulation by athermal suppression of defect production in concentrated solid solution alloys [Supplementary Data] Velişa, G.; Wendler, E.; Zhao, S. Figshare-Supplementary information for journal article at DOI: 10.1080/21663831.2017.1410863, 1 .docx file (2.08 MB) https://doi.org/10.6084/m9.figshare.5711458.v1	preprint	December 2017

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