Results 11 to 20 of about 541 (111)
Additive manufacturing technologies for EUROFER97 components [PDF]
Journal of Nuclear Materials, 2021 By uncoupling the manufacturability from the design process, additive manufacturing of the baseline material EUROFER97 can open significant design freedom for divertor and breeding blankets in fusion technology. As additive manufactured components are known to possess unique microstructures compared to EUROFER97 from standard technologies, the aim of ...
Bonk, Simon +5 more
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Compatibility of EUROFER97 and lead–lithium eutectic [PDF]
Nuclear Materials and Energy, 2023 Information as concerning the compatibility of EUROFER97, or other martensitic steels, and liquid lead–lithium eutectic is collected and evaluated. The best part addresses dissolution caused by the liquid metal, whereas data on the effect on characteristic mechanical properties of the steel are scarce, and even scarcer for the simultaneous influence of
Khanchych, Kateryna, Schroer, Carsten
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Permeation and trapping of hydrogen in Eurofer97
Nuclear Materials and Energy, 2021 Diffusion and trapping of hydrogen isotopes in fusion materials need to be fully described in order to evaluate permeation and retention in fusion reactors walls and breeding blankets. Hydrogen gas permeation experiments have been conducted on Eurofer97 with pressures ranging from 101to 105Pa and temperatures between 473 K and 673 K, resulting in ...
Montupet-Leblond, F. +9 more
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On the lattice coherency of oxide particles dispersed in EUROFER97
Journal of Nuclear Materials, 2009 Oxide dispersion strengthened steels based on the ferritic/martensitic steel EUROFER97 are developed. The reinforcing particles dispersed in the matrix of EUROFER97 are made of yttria and yttrium titanium oxides. Microstructure is investigated by transmission electron microscopy (TEM).
Ramar, A., Baluc, N., Schäublin, R.
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ANSYS Creep-Fatigue Assessment tool for EUROFER97 components [PDF]
Nuclear Materials and Energy, 2016 The damage caused by creep-fatigue is an important factor for materials at high temperatures. For in- vessel components of fusion reactors the material EUROFER97 is a candidate for structural application where it is subjected to irradiation and cyclic thermo-mechanical loads.
Mahler, M., Özkan, F., Aktaa, J.
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Multimodal Investigation Into Laser-welded Proton-irradiated Eurofer97
, 2023 Data repository for "Multimodal Investigation Into Laser-welded Proton-irradiated Eurofer97", product of the project "The Effect of Radiation on Laser Welds for Fusion Applications".
Angus P C Wylie +9 more
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Eurofer97 Creep-Fatigue assessment tool for ANSYS APDL and workbench
Nuclear Materials and Energy, 2018 For the design of future fusion reactors the ferritic-martensitic steel Eurofer97 is the main candidate for in-vessel structural application to be able to withstand harsh environment like irradiation and cyclic loading under elevated temperatures. In case of high temperatures, not only fatigue but also creep damage becomes significant and has to be ...
Mahler, M., Aktaa, J.
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Modeling of Ductile Tearing for RAFM Steel Eurofer97 [PDF]
Procedia Materials Science, 2014 AbstractThe contribution describes experiments and numerical modelling performed to deal with ductile tearing for RAFM steel Eurofer97. Based on results of tensile testing and results of FEA a micromechanical model of ductile fracture Gurson-Tvergaard-Needleman (GTN) was calibrated. This model was then applied for simulation of measured J-R curve.
Stratil, Ludek +3 more
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SANS investigation of proton-irradiated EUROFER97
Journal of Nuclear Materials, 2004 Small angle neutron scattering experiments have been undertaken on the tempered martensitic steel EUROFER97 after proton irradiation at 250 and 350 °C and for doses of 0.3 and 1 dpa. It has been qualitatively shown that the scattering arises from distributions of irradiation-induced defects that peak below one nanometer in size (radius).
Spätig, P. +4 more
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The Influence of Helium and ODS on the Irradiation-Induced Hardening of Eurofer97 at 300°C
Advances in Science and Technology, 2010 The influence of helium on the mechanical properties of reduced-activation ferritic/martensitic Cr-steels under fusion-relevant irradiation conditions is still a concern. While the fact that He can influence the mechanical properties is well established [1,2], the underlying mechanisms are not fully understood [1,2].
Heintze, C. +3 more
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