Radiation effects on the microstructure of a 9Cr-ODS alloy.

Journal Article · Mon Dec 31 23:00:00 EST 2007 · J. Mater.

DOI:https://doi.org/10.1007/s11837-008-0003-5· OSTI ID:1004857

Gan, J; Allen, T R; Birtcher, R C; Shutthanandan, S; Thevothasan, S; INL,; PNNL,

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.

• Research Organization: Argonne National Laboratory (ANL)
• Sponsoring Organization: SC; Univ. of Wisconsin
• DOE Contract Number: AC02-06CH11357
• OSTI ID: 1004857
• Report Number(s): ANL/MSD/JA-68713
• Journal Information: J. Mater., Journal Name: J. Mater. Journal Issue: 1 ; Jan. 2008 Vol. 60; ISSN 1047-4838
• Country of Publication: United States
• Language: ENGLISH

Related Subjects

36 MATERIALS SCIENCE
ALLOYS
DISLOCATIONS
IRRADIATION
MICROSTRUCTURE
NICKEL IONS
OXIDES
RADIATION EFFECTS
REACTORS
SHRINKAGE
STEELS