TY - JOUR
T1 - Radiation damage effects in cubic-stabilized zirconia irradiated with 72 MeV I+ ions
AU - Sickafus, Kurt E.
AU - Matzke, Hansjoachim
AU - Yasuda, Kazuhiro
AU - Chodak, Paul
AU - Verrall, Richard A.
AU - Lucuta, Petru G.
AU - Andrews, H. Robert
AU - Turos, Andrzej
AU - Fromknecht, Rainer
AU - Baker, Neil P.
N1 - Funding Information:
The authors wish to thank M.G. Snow and R.G. Warren of Los Alamos National Laboratory for providing electron microprobe analyses of the zirconia crystals used for this study. Also, the authors from Los Alamos National Laboratory acknowledge the support provided by the Department of Energy, Office of Basic Energy Sciences, Division of Materials Science.
PY - 1998/5
Y1 - 1998/5
N2 - Cubic-stabilized zirconia single crystals were irradiated using 72 MeV I+ ions in the TASSC accelerator facility at Chalk River Laboratory (to simulate a typical U or Pu fission fragment). Irradiations were performed over the fluence range 1 × 1018-5 × 1019 ions/m2, at temperatures of 300, 770, and 1170 K. Damage accumulation was monitored using Rutherford Backscattering Spectroscopy and ion-channeling (RBS/C) techniques. At ambient temperature and at the highest I+ fluence used in these experiments (5 × 1019 I+/m2), RBS/C measurements revealed a rather high degree of lattice disorder. Specifically, the dechanneling parameter χmin varied from 80% to greater than 90% over the depth probed by RBS/C (∼1 μm). Nano-indentation measurements on the same sample indicated decreases in elastic modulus, E, and hardness, H (both by about 9%). These results suggest that an alteration in structure beyond simple defect accumulation occurs under these irradiation conditions. However, transmission electronmicroscopy (TEM) observations and in particular microdiffraction measurements failed to reveal any structural transformations in the irradiated material.
AB - Cubic-stabilized zirconia single crystals were irradiated using 72 MeV I+ ions in the TASSC accelerator facility at Chalk River Laboratory (to simulate a typical U or Pu fission fragment). Irradiations were performed over the fluence range 1 × 1018-5 × 1019 ions/m2, at temperatures of 300, 770, and 1170 K. Damage accumulation was monitored using Rutherford Backscattering Spectroscopy and ion-channeling (RBS/C) techniques. At ambient temperature and at the highest I+ fluence used in these experiments (5 × 1019 I+/m2), RBS/C measurements revealed a rather high degree of lattice disorder. Specifically, the dechanneling parameter χmin varied from 80% to greater than 90% over the depth probed by RBS/C (∼1 μm). Nano-indentation measurements on the same sample indicated decreases in elastic modulus, E, and hardness, H (both by about 9%). These results suggest that an alteration in structure beyond simple defect accumulation occurs under these irradiation conditions. However, transmission electronmicroscopy (TEM) observations and in particular microdiffraction measurements failed to reveal any structural transformations in the irradiated material.
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U2 - 10.1016/S0168-583X(98)00217-1
DO - 10.1016/S0168-583X(98)00217-1
M3 - Article
AN - SCOPUS:0032065024
VL - 141
SP - 358
EP - 365
JO - Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms
JF - Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms
SN - 0168-583X
IS - 1-4
ER -