Microstructural examination of neutron, proton and self-ion irradiation damage in a model Fe9Cr alloy
Source abstract
Abstract
Abstract Transmission electron microscopy (TEM) was used to compare the microstructural defects produced in an Fe9Cr model alloy during exposure to neutrons, protons, or self-ions. Samples from the same model alloy were irradiated using fission-neutrons, 2 MeV Fe+ ions or 1.2 MeV protons at similar temperatures (∼300 °C) and similar doses (∼2.0 dpa). The neutron-irradiated alloy contained visible interstitial dislocation loops with b = 111 , and on average ∼5 nm in size. The density varied from 2±1 × 1020 m-3 (in the matrix far from dislocations and boundaries) to 1.2±0.3 ×1023 m-3 (close to helical dislocation lines). Chromium α′-phase precipitates were also identified at a density of 7.4±0.4 ×1023 m-3. Self-ion irradiation produced mostly homogeneously distributed dislocation loops (6–7 nm on average), and with a greater fraction of 100 loops (∼40%) than was seen in the neutron-irradiated alloy, and at a density of 6.8±0.8 ×1022 m-3. In contrast to the loops produced by neutron irradiation, the self-ion irradiated Fe9Cr contained only vacancy-type loops. Chromium also remained in solution. Proton-irradiated Fe9Cr contained interstitial dislocation loops close to helical-dislocation segments, similar to the neutron-irradiated sample. Chromium α′-phases were also identified in the proton-irradiated sample at a density of 2.5±0.3 ×1023 m-3, and large voids (up to 7 nm) were found at a density over 1022m−3. Like the neutron-irradiated sample, the density of dislocation loops was also heterogeneously distributed; far from grain boundaries and dislocation lines the density was 2.5±0.4 ×1022 m-3, while close to helical dislocation lines the density was 8.1±1.3 ×1022 m-3.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Fusion materials and technologies · Nuclear Materials and Properties · Ion-surface interactions and analysis
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