Corrigendum to “Atom probe study of irradiation-enhanced α′ precipitation in neutron-irradiated Fe–Cr model alloys” [J. Nucl. Mater. 462 (2015) 242–249]

Effect of Laser Shock Peening on the Microstructures and Properties of Oxide‐Dispersion‐Strengthened Austenitic Steels

“…ODS austenitic steels, such as ODS 316, ODS 310, and ODS 304, have been recently developed for next‐generation fossil and nuclear energy systems, such as the very‐high‐temperature reactors (VHTR) . Generally, austenitic steels have better creep resistance than ferritic steels, because the close‐packed face‐centered cubic (FCC) structure is more stable and more resistant to creep than the body‐centered cubic (BCC) structure at high temperatures . On the other hand, ferritic steels have better void swelling resistance than austenitic steels, because the BCC structure results in a reduction of dislocation bias and increased self‐diffusion, which are beneficial for reduced radiation swelling.…”

On the microstructure and strengthening mechanism in oxide dispersion-strengthened 316 steel: A coordinated electron microscopy, atom probe tomography and in situ synchrotron tensile investigation

“…However, the F/M phase of Fe-based alloys, with its low Cr content of less than 9 wt%, has intrinsically poor corrosion resistance, which limits its applications in fuel cladding materials, especially in the supercritical water environment. A higher Cr content may improve the corrosion performance [8], but at the expense of introducing α-α′ phase separation during thermal aging enhanced by neutron irradiation [9,10]. These Cr-enriched α′ precipitates embrittle the material, degrading its ductility and toughness.…”

Neutron-induced damage simulations: Beyond defect production cross-section, displacement per atom and iron-based metrics

“…The latter represent, respectively, a model alloy for reactor pressure vessel (RPV) steels, ferritic martensitic (FM) steels and first wall fusion material, which due to the transmutation establishes a considerable concentration of Re under expected fusion operating conditions. The following four types of pre-existing defects were considered in the MD simulations: i) dislocation loops in pure Fe [100]; ii) solute-rich Ni-Mn-Cu clusters in RPV model alloys, mimicking so-called "late blooming phases" [101]; iii) coherent Cr precipitates, aka α ′ particles, in FM model alloys [102][103][104]; and iv) non-coherent Re precipitates in tungsten [105,106].…”

“…Interstitial dislocation loops were created in pure Fe, as these are the most typical defects appearing under irradiation already at an early stage, when the dose does not exceed 1 dpa (e.g., [107]). The information on the Cr α ′ and Ni-Cu-Mn precipitates was obtained from the available experimental observations (e.g., atom probe, transmission electron microscopy, ...) in the neutron irradiated steels [102][103][104]. Those precipitates are coherent with the bcc Fe matrix, and their typical size ranges from 0.5 nm to few nano-meters, while the density is within 20 23 -20 24 m −3 .…”