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- W3092435009 abstract "The 9Cr-1Mo tempered martensitic steel was irradiated with fast neutrons in the French Phénix reactor. Mechanical tests, density measurement as well as microstructural investigations were carried out following irradiation up to 155 dpa in the temperature range 386°C – 525°C. Tensile, elongation and impact properties were only slightly modified by irradiation. Microstructural investigations revealed the presence of cavities, however the resulting swelling was low (0.1%). In most cases, the dislocation microstructure was arranged in a network. Nevertheless, some large loops were observed after irradiation at 398°C to 112 dpa. Overall, the EM10 steel showed excellent radiation resistance, which confirmed that this steel is an attractive wrapper candidate material for future sodium-cooled GEN IV fast reactors." @default.
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- W3092435009 date "2021-01-01" @default.
- W3092435009 modified "2023-10-14" @default.
- W3092435009 title "Mechanical and microstructural analysis of an EM10 wrapper tube after neutron irradiation in Phénix" @default.
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- W3092435009 doi "https://doi.org/10.1016/j.jnucmat.2020.152575" @default.
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