Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Enhanced structural stability of nanoporous zirconia under irradiation of He

Journal Article · · Journal of Nuclear Materials

This work reports a greatly enhanced tolerance for He irradiation-induced swelling in nanocrystalline zirconia film with interconnected nanoporous structure (hereinafter referred as to NC-C). Compared to bulk yttria-stabilized zirconia (YSZ) and another nanocrystalline zirconia film only with discrete nano voids (hereinafter referred as to NC-V), the NC-C film reveals good tolerance for irradiation of high-fluence He. No appreciable surface blistering can be found even at the highest fluence of 6 1017 cm2 in NCC film. From TEM analysis of as-irradiated samples, the enhanced tolerance for volume swelling in NCC film is attributed to the enhanced diffusion mechanism of deposited He via widely distributed nano channels. Furthermore, the growth of grain size is quite small for both nanocrystalline zirconia films after irradiation, which is ascribed to the decreasing of area of grain boundary due to loose structure and low energy of primary knock-on atoms for He ions.

Research Organization:
Oak Ridge National Laboratory (ORNL)
Sponsoring Organization:
SC USDOE - Office of Science (SC)
DOE Contract Number:
AC05-00OR22725
OSTI ID:
1095737
Journal Information:
Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Journal Issue: 1-3 Vol. 427; ISSN 0022-3115
Country of Publication:
United States
Language:
English

Similar Records

Effects of He Irradiation on Yttria-Stabilized Zirconia Ceramics
Journal Article · Tue Dec 30 23:00:00 EST 2014 · Journal of the American Ceramic Society · OSTI ID:1265427

Radiation tolerance of nanocrystalline ceramics: Insights from yttria stabilized zirconia
Journal Article · Mon Jan 12 23:00:00 EST 2015 · Scientific Reports · OSTI ID:1193481

Damage evolution of yttria-stabilized zirconia induced by He irradiation
Journal Article · Sat Dec 31 23:00:00 EST 2011 · Journal of Nuclear Materials · OSTI ID:1034025

Related Subjects