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|Title:||Radiation Damage Effects in Cubic-Stabilized Zirconia Irradiated with 72 MeV I+ Ions.|
|Authors:||SICKAFUS K.e.; MATZKE Hj.; YASUDA K.; CHODAK P.; VERRALL R.a.; LUCUTA P.g.; ANDREWS R.; TUROS A.; FROMKNECHT R.; BAKER N.p.|
|Citation:||Nuclear Instruments and Methods in Physics Research B vol. B141 p. 358|
|Type:||Articles in periodicals and books|
|Abstract:||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 1x10 18-5x10 19 ions/m2, at temperatures of 300, 770, and 1170 K. Damage accumulation was monitored using Rutheford Backscattering Spectroscopy and ion-channeling (RBS/C) techniques. At ambient temperature and at the highest I+ fluence used in these experiments (5x10 19 I=/m2), RBS/C measurements revealed a rather high degree of latticedisorder. Specifically, the dechanneling parameter chi min varied from 80% to greater than 90% over the depth probed by RBS/C (~1 mu m). 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 electromicroscopy (TEM) observations and in particular microdiffraction measurements failed to reveal any structural transformations in the irradiated material.|
|JRC Institute:||Nuclear Safety and Security|
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