2019 Fall Meeting

Presentation information


Oral presentation

V. Nuclear Fuel Cycle and Nuclear Materials » 502-1 Nuclear Materials, Degradation, Radiation Effects, and Related Technology

[3H10-12] ODS Steel

Fri. Sep 13, 2019 2:45 PM - 3:35 PM Room H (Common Education Bildg. 2F B21)

Chair:Shinichiro Yamashita(JAEA)

2:45 PM - 3:00 PM

[3H10] Neutron irradiation effects on EB-welded Fe−12Cr−6Al ODS steel

*Jin Gao1, Peng Song1, Yen-Jui Huang1, Kiyohiro Yabuuchi1, Akihiko Kimura1 (1. Kyoto Univ.)

Keywords:neutron irradiation , irradiation hardening, dislocation loops, weld

Fe−12Cr−6Al ODS was developed as ATF cladding for its excellent oxidation resistance at very high temperature as well as high strength. Specimens of Fe−12Cr−6Al from both base and electron beam (EB) weld part were neutron irradiated to ~2.6 dpa at 300 °C. Stability of the oxide particles was investigated with respect to the average size and number density. Results showed that the oxide particles showed no significant changes after neutron irradiation in base part. Both the average size and number density of dislocation loops after neutron irradiation were characterized by TEM, in both base part and weld part. The average size of dislocation loops was measured to be (7.6 ± 3.8) nm and (10.0 ± 3.8) nm in base and weld part, respectively. While the number density was estimated to be 1.6 × 1022m-3 and 2.2 × 1022m-3 in base and weld part, respectively. Ion irradiation with 6.4 MeV Fe3+ at the same irradiation condition was compared with neutron irradiation. The similarity and difference was discussed