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

Abstract

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.

Authors:
 [1];  [1];  [2]
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Univ. of Tennessee, Knoxville, TN (United States)
  2. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Publication Date:
Research Org.:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States); Energy Frontier Research Centers (EFRC) (United States). Energy Dissipation to Defect Evolution (EDDE)
Sponsoring Org.:
USDOE Office of Science (SC), Basic Energy Sciences (BES)
OSTI Identifier:
1242668
Alternate Identifier(s):
OSTI ID: 1252043
Grant/Contract Number:  
AC05-00OR22725
Resource Type:
Journal Article: Accepted Manuscript
Journal Name:
Journal of Nuclear Materials
Additional Journal Information:
Journal Volume: 471; Related Information: EDDE partners with Oak Ridge National Laboratory (lead); Lawrence Livermore National Laboratory; University of Michigan; University of Tennessee; University of Wisconsin; University of Wyoming; Virginia Tech; Journal ID: ISSN 0022-3115
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS

Citation Formats

Jin, Ke, Zhang, Yanwen, and Bei, Hongbin. Ion irradiation induced defect evolution in Ni and Ni-based FCC equiatomic binary alloys. United States: N. p., 2015. Web. doi:10.1016/j.jnucmat.2015.09.009.
Jin, Ke, Zhang, Yanwen, & Bei, Hongbin. Ion irradiation induced defect evolution in Ni and Ni-based FCC equiatomic binary alloys. United States. https://doi.org/10.1016/j.jnucmat.2015.09.009
Jin, Ke, Zhang, Yanwen, and Bei, Hongbin. 2015. "Ion irradiation induced defect evolution in Ni and Ni-based FCC equiatomic binary alloys". United States. https://doi.org/10.1016/j.jnucmat.2015.09.009. https://www.osti.gov/servlets/purl/1242668.
@article{osti_1242668,
title = {Ion irradiation induced defect evolution in Ni and Ni-based FCC equiatomic binary alloys},
author = {Jin, Ke and Zhang, Yanwen and Bei, Hongbin},
abstractNote = {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.},
doi = {10.1016/j.jnucmat.2015.09.009},
url = {https://www.osti.gov/biblio/1242668}, journal = {Journal of Nuclear Materials},
issn = {0022-3115},
number = ,
volume = 471,
place = {United States},
year = {Wed Sep 09 00:00:00 EDT 2015},
month = {Wed Sep 09 00:00:00 EDT 2015}
}

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Cited by: 39 works
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Works referenced in this record:

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Works referencing / citing this record:

Direct Observation of Defect Range and Evolution in Ion-Irradiated Single Crystalline Ni and Ni Binary Alloys
journal, February 2016


Delayed damage accumulation by athermal suppression of defect production in concentrated solid solution alloys [Supplementary Data]
preprint, December 2017


Delayed damage accumulation by athermal suppression of defect production in concentrated solid solution alloys
journal, December 2017


Effects of chemical alternation on damage accumulation in concentrated solid-solution alloys
journal, June 2017


Direct Observation of Defect Range and Evolution in Ion-Irradiated Single Crystalline Ni and Ni Binary Alloys
journal, February 2016