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Title: The effect of injected interstitials on void formation in self-ion irradiated nickel containing concentrated solid solution alloys

Pure nickel and three nickel containing single-phase concentrated solid solution alloys (SP-CSAs) have been irradiated using 3 MeV Ni 2+ ions at 500 C to fluences of 1.5 x 10 16 and 5.0 x 10 16 cm 2. We characterized the radiation-induced voids using cross sectional transmission electron microscopy that distributions of voids and dislocation loops were presented as a function of depth. We also observed a various degree of void suppression on the tested samples and a defect clusters migration mechanism was proposed for NiCo. Furthermore, in order to sufficiently understand the defect dynamics in these SP-CSAs, the injected interstitial effect has been taken into account along with the 1-dimentional (1-D) and 3-dimentional (3-D) interstitial movement mechanisms.
Authors:
 [1] ;  [1] ;  [2] ;  [3] ;  [2] ;  [4] ;  [2] ;  [5]
  1. Univ. of Michigan, Ann Arbor, MI (United States). Dept. of Nuclear Engineering and Radiological Sciences
  2. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Materials Science and Technology Division
  3. Univ. of Tennessee, Knoxville, TN (United States). Dept. of Materials Science and Engineering
  4. (United States). Dept. of Materials Science and Engineering
  5. Univ. of Michigan, Ann Arbor, MI (United States). Dept. of Nuclear Engineering and Radiological Sciences and Dept. of Materials Science Engineering
Publication Date:
Grant/Contract Number:
AC05-00OR22725
Type:
Accepted Manuscript
Journal Name:
Journal of Nuclear Materials
Additional Journal Information:
Journal Volume: 488; Journal Issue: C; Journal ID: ISSN 0022-3115
Publisher:
Elsevier
Research Org:
Oak Ridge National Lab. (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) (SC-22)
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; Injected interstitials; Irradiation effects; Ni containing concentrated solid solution alloys; Void Swelling
OSTI Identifier:
1354672
Alternate Identifier(s):
OSTI ID: 1396895

Yang, Tai-ni, Lu, Chenyang, Jin, Ke, Crespillo, Miguel L., Zhang, Yanwen, Univ. of Tennessee, Knoxville, TN, Bei, Hongbin, and Wang, Lumin. The effect of injected interstitials on void formation in self-ion irradiated nickel containing concentrated solid solution alloys. United States: N. p., Web. doi:10.1016/j.jnucmat.2017.02.026.
Yang, Tai-ni, Lu, Chenyang, Jin, Ke, Crespillo, Miguel L., Zhang, Yanwen, Univ. of Tennessee, Knoxville, TN, Bei, Hongbin, & Wang, Lumin. The effect of injected interstitials on void formation in self-ion irradiated nickel containing concentrated solid solution alloys. United States. doi:10.1016/j.jnucmat.2017.02.026.
Yang, Tai-ni, Lu, Chenyang, Jin, Ke, Crespillo, Miguel L., Zhang, Yanwen, Univ. of Tennessee, Knoxville, TN, Bei, Hongbin, and Wang, Lumin. 2017. "The effect of injected interstitials on void formation in self-ion irradiated nickel containing concentrated solid solution alloys". United States. doi:10.1016/j.jnucmat.2017.02.026. https://www.osti.gov/servlets/purl/1354672.
@article{osti_1354672,
title = {The effect of injected interstitials on void formation in self-ion irradiated nickel containing concentrated solid solution alloys},
author = {Yang, Tai-ni and Lu, Chenyang and Jin, Ke and Crespillo, Miguel L. and Zhang, Yanwen and Univ. of Tennessee, Knoxville, TN and Bei, Hongbin and Wang, Lumin},
abstractNote = {Pure nickel and three nickel containing single-phase concentrated solid solution alloys (SP-CSAs) have been irradiated using 3 MeV Ni2+ ions at 500 C to fluences of 1.5 x 1016 and 5.0 x 1016 cm2. We characterized the radiation-induced voids using cross sectional transmission electron microscopy that distributions of voids and dislocation loops were presented as a function of depth. We also observed a various degree of void suppression on the tested samples and a defect clusters migration mechanism was proposed for NiCo. Furthermore, in order to sufficiently understand the defect dynamics in these SP-CSAs, the injected interstitial effect has been taken into account along with the 1-dimentional (1-D) and 3-dimentional (3-D) interstitial movement mechanisms.},
doi = {10.1016/j.jnucmat.2017.02.026},
journal = {Journal of Nuclear Materials},
number = C,
volume = 488,
place = {United States},
year = {2017},
month = {2}
}