Neutron irradiation effects on the mechanical properties of dispersion-strengthened steels
1979; Elsevier BV; Volume: 85-86; Linguagem: Inglês
10.1016/0022-3115(79)90379-9
ISSN1873-4820
AutoresHideo Kayano, K. Suganuma, Minoru Narui, Shigeru Suzuki, Shunsuke Yajima,
Tópico(s)Nuclear reactor physics and engineering
ResumoAlloy powder particles of Fe-13Cr ferritic steel (SUS 410 stainless steel) are coated with 3% thin films of organometallic complexes or titanium alkoxides and are then subjected to thermal decomposition. Thus a dispersion-strengthened ferritic steel has been explored in which the fine particle carbide and the oxide are uniformly dispersed. The mechanical properties of sintered Fe-13Cr alloys are compared with those of a Fe-13Cr alloy containing 3% commercial TiO2 powder. The results show that the samples containing organometallic complexes and alkoxides are increased in strength at room temperature and 600°C as compared with those without the additions. In particular, an increase in both strength and elongation is observed in the samples to which 3% of titanium acetylacetonate is added as the organometallic complex. Neutron irradiation to a fluence of 2.6 × 1019n/cm2 (>1 MeV) has been performed to examine the mechanical properties. A decrease in elongation with an increase in strength is observed as the result of the irradiation. The decrease in elongation is found to be smallest in the sample containing 3% of titanium acetylacetonate. No void is observed with a high voltage electron microscope when electron irradiated up to 13 dpa at 400–450°C.
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