@article{bd1d8b45a79041dea3200255e0ec8317,
title = "Radiation effects on the microstructure of a 9Cr-ODS alloy",
abstract = "Oxide dispersion strengthened (ODS) steels are prime candidates for high-temperature, high-dose cladding in advanced nuclear reactors. When a 9Cr-ODS alloy was irradiated with 5 MeV nickel ions at temperatures of 500-700°C to doses up to 150 dpa, there was no significant change in the dislocation arrangement. For oxide particles, there is a small shrinkage in size and increase in density with increasing irradiation dose. This work confirms that oxide particles and the microstructure of the 9Cr-ODS show minimal changes under irradiation at temperatures up to 700°C and doses up to 150 dpa.",
author = "Jian Gan and Allen, \{T. R.\} and Birtcher, \{R. C.\} and S. Shutthanandan and S. Thevuthasan",
note = "Funding Information: This work was funded by the U.S. Department of Energy (DOE) through a Nuclear Energy Research Initiative program at the Idaho National Labora tory and the University of Wisconsin. A portion of the research was performed in the William R. Wiley Environmental Molecular Science Laboratory, a DOE user facility funded by the Office of Biological and Environmental Research. Pacific Northwest National Laboratory is a multiprogram national laboratory operated for the DOE by the Battelle Memorial Institute under Contract DE-AC06-76RLO 1830. A portion of the experimental part of this research was conducted at the IVEM-Accelerator User Facility at Argonne National Laboratory, which is sponsored by the Division of Scientific User Facilities, Office of Basic Energy Science, DOE. The authors are grateful to the Japan Atomic Energy Agency for providing the 9Cr-ODS alloy.",
year = "2008",
month = jan,
doi = "10.1007/s11837-008-0003-5",
language = "English",
volume = "60",
pages = "24--28",
journal = "JOM",
issn = "1047-4838",
publisher = "Minerals, Metals and Materials Society",
number = "1",
}