Fluence and helium effects on the tensile properties of ferritic steels at low temperatures☆
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Cited by (43)
Machine learning-based predictions of yield strength for neutron-irradiated ferritic/martensitic steels
2023, Fusion Engineering and DesignThe effects of high energy deuteron ion beam irradiation on the tensile behavior of HT-9
2022, Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and AtomsCitation Excerpt :The fidelity and reliability of mechanical testing is similarly of interest, given the rising popularity of smaller length scale testing [10,11]. Traditionally, reactors or accelerators are used to irradiate materials for performance testing [1–9,12]. Both approaches benefit from smaller material testing techniques.
Influence of proton irradiation on the microstructure and mechanical properties of Nb-1Zr-0.1C alloy
2021, Journal of Nuclear MaterialsCitation Excerpt :The increase in nanohardness (Fig. 15) also indicated the formation of more dislocation loops as a result of irradiation. Irradiation induced loss of ductility have been observed in other BCC alloys [58–61]. This has been mostly attributed to occurrence of heterogeneous localized deformation due to the formation of dislocation channels [62–65].
Microstructural changes of ferritic/martensitic steels after irradiation in spallation target environments
2018, Journal of Nuclear MaterialsCitation Excerpt :To help readers to get a better understanding of the main outcome of these microstructural analyses, together with few new results we summarize and also reanalyze the results in this review paper. In this paper, TEM results on FM steels T91 (ORNL Heat 30176 [38] and SPIRE Heat [39]), F82H (IEA Heat 9741 [40,41], Eurofer-97 [42,43] and CLAM [44], PAS results on F82H, Eurofer-97, Optifer-IX [45], CLAM and ODS-Eurofer 97 (Heat 0449 [46]), and APT results of F82H and Manet-II (Heat 50761 [47]) are presented. The detailed information of chemical composition and heat treatment conditions of these FM steels can also be found in Ref. [43].
Crystal plasticity investigation of the microstructural factors influencing dislocation channeling in a model irradiated bcc material
2016, Acta MaterialiaCitation Excerpt :Moreover, damage (micro-crack) nucleation and propagation is also expected to contribute to flow localization at higher strains (cf. Ref. [67] for the description of a void nucleation and growth based damage framework for modeling relevant phenomena). We note that initiation of macroscopic flow localization and drop in flow stress occurs in the present case at relatively longer elongations (∼0.75–1.25% nominal strain), as compared to other materials, such as ferritic/martensitic F82H steel [2], ferritic/martensitic Cr-Mo steels [14], and Mo-Re alloys [19], where similar phenomena were observed earlier at 0.2–0.6% nominal strains. However, this is a material-dependent phenomena and the simulated stress-strain response, in the present case, is simply based on model calibration to the experimental stress-strain response of a ferritic/martensitic Mod 9Cr-1Mo steel [16], which demonstrates a relatively enhanced uniform elongation.
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Research sponsored by the office of Fusion Energy, US Department of Energy under contract DE-AC05-64OR21400 with Martin Marietta Energy Systems, Inc.