Irradiation behavior evaluation of oxide dispersion strengthened ferritic steel cladding tubes irradiated in JOYO
2013; Elsevier BV; Volume: 442; Issue: 1-3 Linguagem: Inglês
10.1016/j.jnucmat.2013.04.051
ISSN1873-4820
AutoresShinichiro Yamashita, Yasuhide Yano, Satoshi Ohtsuka, Tsunemitsu Yoshitake, Takeji Kaito, Shin-ichi Koyama, Kenya Tanaka,
Tópico(s)Nuclear Physics and Applications
ResumoIrradiation behavior of ODS steel cladding tubes was evaluated for the further progress in understanding of the neutron-irradiation effects on ODS steel. Two types of ODS (9Cr–ODS_F/M, 12Cr–ODS_F) steel cladding tubes with differences in basic compositions and matrix phases were irradiated in JOYO. Post-irradiation examination data concerning hardness, ring tensile property, and microstructure were obtained. Hardness measurement after irradiation showed that there was an apparent irradiation temperature dependence on hardness for 9Cr–ODS_F/M steel whereas no distinct temperature dependence for 12Cr–ODS_F steel. Also, there was no significant change in tensile strengths after irradiation below 923 K, but those above 1023 K up to 6.6 × 1026 n/m2 (E > 0.1 MeV) were decreased by about 20%. TEM observations showed that the radiation-induced defect cluster formation during irradiation was suppressed because of high density sink site for defect such as initially-existed dislocation, and precipitate interfaces. In addition, oxide particles were stable up to the maximum doses of this irradiation test.
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