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Title: Investigation of the thermal and neutron irradiation response of BAM-11 bulk metallic glass

Abstract

Zr52.5Cu17.9Ni14.6Al10Ti5 (BAM-11) bulk metallic glass was irradiated by neutrons to a fluence of 1.4 × 1020 n/cm2 (E > 0.1 MeV) (0.1 displacements per atom, dpa) at a temperature of ~70 °C and then assessed using multiple mechanical property and structural characterization techniques. Nanoindentation hardness measurements revealed that irradiation led to softening and a reduced Young's modulus in the alloy while annealing at 300–325 °C caused an increase in the hardness and modulus. Neutron diffraction results indicated that primary knock-on events caused rejuvenation (structural disordering) while annealing resulted in structural relaxation. Furthermore, it was found that annealing after irradiation reversed the disordering effects caused by the irradiation. The increased disordering in the alloy during irradiation is thought to be attributed to the enhanced free volume content caused by the neutron collision cascades in the matrix. Indeed, immersion density measurements revealed that irradiation led to a decrease in the density of the alloy. This decrease in the macroscopic density was linked to an increase in the structural disorder of the alloy while an increase in the density corresponded to an increasing degree of order. Moreover, synchrotron X-ray diffraction related the structural relaxation of the alloy to a loss of ductility, whichmore » is in agreement with the literature. Generally, an increase in the structural disorder in the sample is linked to a softening of the alloy and to a higher concentration of soft-zone defects in the glass.« less

Authors:
 [1];  [2];  [3];  [2];  [2]; ORCiD logo [1]; ORCiD logo [1];  [1];  [1]
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  2. Univ. of Tennessee, Knoxville, TN (United States)
  3. Framatome Inc., Charlotte, NC (United States)
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE Office of Science (SC), Basic Energy Sciences (BES) (SC-22). Materials Sciences & Engineering Division; USDOE
OSTI Identifier:
1561626
Alternate Identifier(s):
OSTI ID: 1560753
Grant/Contract Number:  
AC05-00OR22725; SC0006661; AC02-06CH11357
Resource Type:
Accepted Manuscript
Journal Name:
Journal of Nuclear Materials
Additional Journal Information:
Journal Volume: 526; Journal Issue: 1; Journal ID: ISSN 0022-3115
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; Metallic glasses; Irradiation effects; Annealing; Microstructure; Nanoindentation; Neutron diffraction

Citation Formats

Brechtl, Jamieson, Wang, Hui, Nimishakavi, Kiran, Yang, T., Lin, Yan-Ru, Bei, Hongbin, Neuefeind, Joerg C., Dmowski, Wojciech, and Zinkle, Steven J. Investigation of the thermal and neutron irradiation response of BAM-11 bulk metallic glass. United States: N. p., 2019. Web. doi:10.1016/j.jnucmat.2019.151771.
Brechtl, Jamieson, Wang, Hui, Nimishakavi, Kiran, Yang, T., Lin, Yan-Ru, Bei, Hongbin, Neuefeind, Joerg C., Dmowski, Wojciech, & Zinkle, Steven J. Investigation of the thermal and neutron irradiation response of BAM-11 bulk metallic glass. United States. https://doi.org/10.1016/j.jnucmat.2019.151771
Brechtl, Jamieson, Wang, Hui, Nimishakavi, Kiran, Yang, T., Lin, Yan-Ru, Bei, Hongbin, Neuefeind, Joerg C., Dmowski, Wojciech, and Zinkle, Steven J. Thu . "Investigation of the thermal and neutron irradiation response of BAM-11 bulk metallic glass". United States. https://doi.org/10.1016/j.jnucmat.2019.151771. https://www.osti.gov/servlets/purl/1561626.
@article{osti_1561626,
title = {Investigation of the thermal and neutron irradiation response of BAM-11 bulk metallic glass},
author = {Brechtl, Jamieson and Wang, Hui and Nimishakavi, Kiran and Yang, T. and Lin, Yan-Ru and Bei, Hongbin and Neuefeind, Joerg C. and Dmowski, Wojciech and Zinkle, Steven J.},
abstractNote = {Zr52.5Cu17.9Ni14.6Al10Ti5 (BAM-11) bulk metallic glass was irradiated by neutrons to a fluence of 1.4 × 1020 n/cm2 (E > 0.1 MeV) (0.1 displacements per atom, dpa) at a temperature of ~70 °C and then assessed using multiple mechanical property and structural characterization techniques. Nanoindentation hardness measurements revealed that irradiation led to softening and a reduced Young's modulus in the alloy while annealing at 300–325 °C caused an increase in the hardness and modulus. Neutron diffraction results indicated that primary knock-on events caused rejuvenation (structural disordering) while annealing resulted in structural relaxation. Furthermore, it was found that annealing after irradiation reversed the disordering effects caused by the irradiation. The increased disordering in the alloy during irradiation is thought to be attributed to the enhanced free volume content caused by the neutron collision cascades in the matrix. Indeed, immersion density measurements revealed that irradiation led to a decrease in the density of the alloy. This decrease in the macroscopic density was linked to an increase in the structural disorder of the alloy while an increase in the density corresponded to an increasing degree of order. Moreover, synchrotron X-ray diffraction related the structural relaxation of the alloy to a loss of ductility, which is in agreement with the literature. Generally, an increase in the structural disorder in the sample is linked to a softening of the alloy and to a higher concentration of soft-zone defects in the glass.},
doi = {10.1016/j.jnucmat.2019.151771},
journal = {Journal of Nuclear Materials},
number = 1,
volume = 526,
place = {United States},
year = {Thu Aug 29 00:00:00 EDT 2019},
month = {Thu Aug 29 00:00:00 EDT 2019}
}

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