Characterization of Grain Boundary Segregation in Ferritic/Martensitic Steel after Irradiation in SINQ Target 4 | Zendy

Lijuan Cui | Zendy; Yong Dai | Zendy; Stephan Gerstl | Zendy; M.A. Pouchon | Zendy; Xin Huang | Zendy; MarcGeorg Willinger | Zendy; R. Schäublin | Zendy

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Characterization of Grain Boundary Segregation in Ferritic/Martensitic Steel after Irradiation in SINQ Target 4

Author(s) -

Lijuan Cui,

Yong Dai,

Stephan Gerstl,

M.A. Pouchon,

Xin Huang,

MarcGeorg Willinger,

R. Schäublin

Publication year - 2020

Language(s) - English

Resource type - Conference proceedings

DOI - 10.7566/jpscp.28.061006

Subject(s) - grain boundary , materials science , characterization (materials science) , martensite , irradiation , metallurgy , microstructure , nanotechnology , physics , nuclear physics

Ferritic/martensitic (FM) steels are major structural materials irradiated in the targets of Swiss Spallation Neutron Source (SINQ). The post-irradiation examination (PIE) of irradiated FM specimens show strong degradation of mechanical properties after irradiation, particularly at dose >10 dpa. As it is known radiation-induced segregation (RIS) could greatly affect the fracture properties of irradiated materials, RIS at grain boundary has been studied with atom probe tomography (APT) in this work. Some interesting results have been obtained from 3 FM steels (F82H, Eurofer 97, and ODS Eurofer) irradiated to 20 dpa.

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