Phase stability and microstructural evolution in neutron-irradiated ferritic-martensitic steel HT9

JOURNAL OF NUCLEAR MATERIALS

卷:557

Article

Yan, Huan¹  Liu, Xiang²  He, Lingfeng²  Stubbins, James¹ 

[1] Univ Illinois, Urbana, IL 61801 USA

[2] Idaho Natl Lab, Idaho Falls, ID USA

关键词: F/M steel;    HT9;    Neutron irradiation;    Dislocation loop;    Irradiation hardening;   

DOI  :  10.1016/j.jnucmat.2021.153252

来源: Elsevier

【 摘 要 】

Ferritic Martensitic (F/M) steel HT9 specimens were irradiated in the Advanced Test Reactor up to 4.16 dpa in three temperature ranges (roughly from 300 to 600 degrees C). The post-irradiation microstructure, including dislocation structure, precipitation and radiation-induced segregation (RIS) was characterized using analytical scanning / transmission electron microscopy (S/TEM), and atom probe tomography (APT). Irradiation hardening was measured using nanoindentation. The results reveal a distinctive pattern of dislocation and precipitate evolution at high temperature, around 600 degrees C, where various defects and precipitates formed in the low dose regime followed by a recovering process with increasing dose. Dislocation loops formed in all temperature ranges, and the growth of dislocation loops is unconstrained above certain critical temperature, contributing to the increasing dislocation density even prior to doses of 0.5 dpa at 600 degrees C. Ni/Mn/Si clusters were identified in all temperature ranges and the compositions of these clusters converged to G phase stoichiometrically. Significant coarsening of G phase particles was observed at 600 degrees C, accompanied by the formation of G phase on grain boundaries. alpha' precipitates were only found in the medium and low temperature ranges (below 500 degrees C). The number density and volume fraction were higher in the low temperature specimens, while larger particles were observed in the medium temperature range. RIS of Cr, Ni, Mn, Si, P was identified at dislocation lines, grain boundaries and phase boundaries, and the temperature dependence is consistent with previous studies. The RIS of Cr to the existing VN particles was confirmed by APT and may accelerate the transition of VN to Cr-rich nitrides. The irradiation hardening contribution from dislocation loops, dislocation lines, G phase and alpha' phase was parsed based on a linear dispersed barrier hardening model. The results suggest that most irradiation hardening at high temperature is due to increasing dislocation density with dose. (C) 2021 Elsevier B.V. All rights reserved.

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