Interstitial migration behavior and defect evolution in ion irradiated pure nickel and Ni-xFe binary alloys

Lu, Chenyang; Yang, Taini; Niu, Liangliang; Peng, Qing; Jin, Ke; Crespillo, Miguel L.; Velisa, Gihan; Xue, Haizhou; Zhang, Feifei; Xiu, Pengyuan; Zhang, Yanwen; Gao, Fei; Bei, Hongbin; Weber, William J.; Wang, Lumin

doi:10.1016/j.jnucmat.2018.07.006

Title: Interstitial migration behavior and defect evolution in ion irradiated pure nickel and Ni-xFe binary alloys

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Abstract

Transition from long-range one-dimensional to short-range three-dimensional migration modes of interstitial defect clusters greatly reduces the damage accumulation in single-phase concentrated solid solution alloys under ion irradiation. A synergetic investigation with experimental, computational and modeling approaches revealed that both the resistance to void swelling and the delay in dislocation evolution in Ni-Fe alloys increased with iron concentration. This was attributed to the gradually increased sluggishness of defect migration, which enhances interstitial and vacancy recombination. Transition from long-range one-dimensional defect motion in pure nickel to short-range three-dimensional motion in concentrated Ni-Fe alloys is continuum, not abrupt, and within an iron concentration range up to 20%. Lastly, the gradual transition process can be quantitatively characterized by the mean free path of the interstitial defect clusters.

Authors:

Lu, Chenyang ^[1]; Yang, Taini ^[1]; Niu, Liangliang ^[1];

^[1];

^[2]; Crespillo, Miguel L. ^[3];

^[2]; Xue, Haizhou ^[3]; Zhang, Feifei ^[1]; Xiu, Pengyuan ^[1];

^[4]; Gao, Fei ^[5];

^[2];

^[3]; Wang, Lumin ^[5]

Univ. of Michigan, Ann Arbor, MI (United States). Dept. of Nuclear Engineering and Radiological Sciences
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Materials Science & Technology Division
Univ. of Tennessee, Knoxville, TN (United States). Dept. of Materials Science and Engineering
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Materials Science & Technology Division; Univ. of Tennessee, Knoxville, TN (United States). Dept. of Materials Science and Engineering
Univ. of Michigan, Ann Arbor, MI (United States). Dept. of Nuclear Engineering and Radiological Sciences, and Dept. of Materials Science and Engineering

Publication Date:: Mon Oct 01 00:00:00 EDT 2018

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

Sponsoring Org.:: USDOE Office of Science (SC), Basic Energy Sciences (BES)

OSTI Identifier:: 1482442

Alternate Identifier(s):: OSTI ID: 1548035

Grant/Contract Number:: AC05-00OR22725

Resource Type:: Accepted Manuscript

Journal Name:: Journal of Nuclear Materials

Additional Journal Information:: Journal Volume: 509; Journal Issue: C; Journal ID: ISSN 0022-3115

Publisher:: Elsevier

Country of Publication:: United States

Language:: English

Subject:: 36 MATERIALS SCIENCE

Citation Formats


                    Lu, Chenyang, Yang, Taini, Niu, Liangliang, Peng, Qing, Jin, Ke, Crespillo, Miguel L., Velisa, Gihan, Xue, Haizhou, Zhang, Feifei, Xiu, Pengyuan, Zhang, Yanwen, Gao, Fei, Bei, Hongbin, Weber, William J., and Wang, Lumin. Interstitial migration behavior and defect evolution in ion irradiated pure nickel and Ni-xFe binary alloys.  United States: N. p., 2018. 
Web.  doi:10.1016/j.jnucmat.2018.07.006.

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                    Lu, Chenyang, Yang, Taini, Niu, Liangliang, Peng, Qing, Jin, Ke, Crespillo, Miguel L., Velisa, Gihan, Xue, Haizhou, Zhang, Feifei, Xiu, Pengyuan, Zhang, Yanwen, Gao, Fei, Bei, Hongbin, Weber, William J., & Wang, Lumin. Interstitial migration behavior and defect evolution in ion irradiated pure nickel and Ni-xFe binary alloys.  United States.  https://doi.org/10.1016/j.jnucmat.2018.07.006

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                    Lu, Chenyang, Yang, Taini, Niu, Liangliang, Peng, Qing, Jin, Ke, Crespillo, Miguel L., Velisa, Gihan, Xue, Haizhou, Zhang, Feifei, Xiu, Pengyuan, Zhang, Yanwen, Gao, Fei, Bei, Hongbin, Weber, William J., and Wang, Lumin. Mon .  
"Interstitial migration behavior and defect evolution in ion irradiated pure nickel and Ni-xFe binary alloys".  United States.  https://doi.org/10.1016/j.jnucmat.2018.07.006.  https://www.osti.gov/servlets/purl/1482442.

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@article{osti_1482442,

  title        = {Interstitial migration behavior and defect evolution in ion irradiated pure nickel and Ni-xFe binary alloys},

  author       = {Lu, Chenyang and Yang, Taini and Niu, Liangliang and Peng, Qing and Jin, Ke and Crespillo, Miguel L. and Velisa, Gihan and Xue, Haizhou and Zhang, Feifei and Xiu, Pengyuan and Zhang, Yanwen and Gao, Fei and Bei, Hongbin and Weber, William J. and Wang, Lumin},

  abstractNote = {Transition from long-range one-dimensional to short-range three-dimensional migration modes of interstitial defect clusters greatly reduces the damage accumulation in single-phase concentrated solid solution alloys under ion irradiation. A synergetic investigation with experimental, computational and modeling approaches revealed that both the resistance to void swelling and the delay in dislocation evolution in Ni-Fe alloys increased with iron concentration. This was attributed to the gradually increased sluggishness of defect migration, which enhances interstitial and vacancy recombination. Transition from long-range one-dimensional defect motion in pure nickel to short-range three-dimensional motion in concentrated Ni-Fe alloys is continuum, not abrupt, and within an iron concentration range up to 20%. Lastly, the gradual transition process can be quantitatively characterized by the mean free path of the interstitial defect clusters.},

  doi          = {10.1016/j.jnucmat.2018.07.006},

  journal      = {Journal of Nuclear Materials},

  number       = C,

  volume       = 509,

  place        = {United States},

  year         = {Mon Oct 01 00:00:00 EDT 2018},

  month        = {Mon Oct 01 00:00:00 EDT 2018}

}

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