The effect of injected interstitials on void formation in self-ion irradiated nickel containing concentrated solid solution alloys
Abstract
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.
- Authors:
-
- 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 and Technology Division
- Univ. of Tennessee, Knoxville, TN (United States). Dept. of Materials Science and Engineering
- (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 Engineering
- Publication Date:
- 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)
- OSTI Identifier:
- 1354672
- Alternate Identifier(s):
- OSTI ID: 1396895
- Grant/Contract Number:
- AC05-00OR22725
- Resource 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
- 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
Citation Formats
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., 2017.
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. https://doi.org/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. Tue .
"The effect of injected interstitials on void formation in self-ion irradiated nickel containing concentrated solid solution alloys". United States. https://doi.org/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 = {Tue Feb 21 00:00:00 EST 2017},
month = {Tue Feb 21 00:00:00 EST 2017}
}
Web of Science