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Title: Potential benefit of amorphization in the retention of gaseous species in irradiated pyrochlores

Abstract

Understanding the structure-property relationship for materials destined for irradiation extremes is a key step in developing materials with reliable, long-term performance. One crucial relationship is the ability of a material to withstand or accommodate amorphization, as this dictates its potential use as a nuclear waste form. Pyrochlores are one such class of materials for consideration as waste forms and there has been significant work examining how both the crystal structure and chemistry impacts amorphization resistance, leading to the important conclusion that the amorphization resistance of pyrochlores (A2B2O7) is very sensitive to the nature of the B cations. For example, pyrochlores with B=Ti amorphize much more readily than B=Zr compounds. However, there are still questions regarding how these types of materials respond to prolonged or high-dose irradiation conditions. Gd2Ti2O7 (GTO) and Gd2Zr2O7 (GZO) pyrochlores were implanted with 400 keV Kr++ ions at room temperature to calculated peak damages of 119 and 135 displacements per atom (dpa), respectively. As expected, GTO amorphized completely under irradiation. However, discrete bubbles of Kr coalesced within the amorphous matrix without micro-cracking or spallation. In contrast, GZO transforms to a disordered fluorite structure under irradiation with no indications of localized amorphization. But, the accumulation of Kr withinmore » the host material leads to sub-grain structures, extended defects, and the development of micro-cracks. Thus, while GTO readily amorphizes even under low dose irradiations, the resistance of the amorphous GTO matrix to micro cracking and gas release, even in the presence of large bubble formation, suggests an enhanced propensity to retain gaseous species. Finally, consideration of long-term dose accumulation effects in nuclear waste forms would suggest reconsideration of amorphization processes in pyrochlores and related materials as a potential beneficial effect for immobilization and long-term storage of actinide materials.« less

Authors:
ORCiD logo [1];  [1];  [1]; ORCiD logo [1]; ORCiD logo [1]
  1. Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Publication Date:
Research Org.:
Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Sponsoring Org.:
USDOE Office of Science (SC), Basic Energy Sciences (BES); USDOE National Nuclear Security Administration (NNSA)
OSTI Identifier:
1482005
Alternate Identifier(s):
OSTI ID: 1636974
Report Number(s):
LA-UR-18-25544
Journal ID: ISSN 1359-6454
Grant/Contract Number:  
AC52-06NA25396; 2013LANL8400
Resource Type:
Accepted Manuscript
Journal Name:
Acta Materialia
Additional Journal Information:
Journal Volume: 164; Journal ID: ISSN 1359-6454
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; pyrochlore microscopy amorphous irradiation

Citation Formats

Holesinger, Terry G., Valdez, James A., Janish, Matthew T., Wang, Yongqiang, and Uberuaga, Blas P. Potential benefit of amorphization in the retention of gaseous species in irradiated pyrochlores. United States: N. p., 2018. Web. doi:10.1016/j.actamat.2018.10.049.
Holesinger, Terry G., Valdez, James A., Janish, Matthew T., Wang, Yongqiang, & Uberuaga, Blas P. Potential benefit of amorphization in the retention of gaseous species in irradiated pyrochlores. United States. https://doi.org/10.1016/j.actamat.2018.10.049
Holesinger, Terry G., Valdez, James A., Janish, Matthew T., Wang, Yongqiang, and Uberuaga, Blas P. Mon . "Potential benefit of amorphization in the retention of gaseous species in irradiated pyrochlores". United States. https://doi.org/10.1016/j.actamat.2018.10.049. https://www.osti.gov/servlets/purl/1482005.
@article{osti_1482005,
title = {Potential benefit of amorphization in the retention of gaseous species in irradiated pyrochlores},
author = {Holesinger, Terry G. and Valdez, James A. and Janish, Matthew T. and Wang, Yongqiang and Uberuaga, Blas P.},
abstractNote = {Understanding the structure-property relationship for materials destined for irradiation extremes is a key step in developing materials with reliable, long-term performance. One crucial relationship is the ability of a material to withstand or accommodate amorphization, as this dictates its potential use as a nuclear waste form. Pyrochlores are one such class of materials for consideration as waste forms and there has been significant work examining how both the crystal structure and chemistry impacts amorphization resistance, leading to the important conclusion that the amorphization resistance of pyrochlores (A2B2O7) is very sensitive to the nature of the B cations. For example, pyrochlores with B=Ti amorphize much more readily than B=Zr compounds. However, there are still questions regarding how these types of materials respond to prolonged or high-dose irradiation conditions. Gd2Ti2O7 (GTO) and Gd2Zr2O7 (GZO) pyrochlores were implanted with 400 keV Kr++ ions at room temperature to calculated peak damages of 119 and 135 displacements per atom (dpa), respectively. As expected, GTO amorphized completely under irradiation. However, discrete bubbles of Kr coalesced within the amorphous matrix without micro-cracking or spallation. In contrast, GZO transforms to a disordered fluorite structure under irradiation with no indications of localized amorphization. But, the accumulation of Kr within the host material leads to sub-grain structures, extended defects, and the development of micro-cracks. Thus, while GTO readily amorphizes even under low dose irradiations, the resistance of the amorphous GTO matrix to micro cracking and gas release, even in the presence of large bubble formation, suggests an enhanced propensity to retain gaseous species. Finally, consideration of long-term dose accumulation effects in nuclear waste forms would suggest reconsideration of amorphization processes in pyrochlores and related materials as a potential beneficial effect for immobilization and long-term storage of actinide materials.},
doi = {10.1016/j.actamat.2018.10.049},
journal = {Acta Materialia},
number = ,
volume = 164,
place = {United States},
year = {Mon Oct 29 00:00:00 EDT 2018},
month = {Mon Oct 29 00:00:00 EDT 2018}
}

Journal Article:

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Cited by: 7 works
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Figures / Tables:

Figure 1 Figure 1: SRIM estimates of the peak damage and Kr deposition profiles as a function of thickness from the sample surface for a 400 keV Kr irradiation dose of 5.36 x 1016 Kr/cm2 for (a) Gd2Ti2O7 and (b) Gd2Zr2O7.

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Figures/Tables have been extracted from DOE-funded journal article accepted manuscripts.