I. Ipatova G. Greaves D. Terentyev M.R. Gilbert Y.-L. Chiu
Helium-induced defect nucleation and accumulation in polycrystalline W and W-0.5wt.%ZrC (W-ZrC) were studied in-situ using the transmission electron microscopy (TEM) combined with 40 keV He+ irradiation at 800 and 1000 °С at the maximum damage level of 1 dpa. Radiation-induced dislocation loops were not observed in the current…
PublishedGerald Pintsuk Giaocomo Aiello Sergei L. Dudarev Michael Gorley Jean Henry Marianne Richou Michael Rieth D. Terentyev Rafael Vila
The EUROfusion materials research program for DEMO in-vessel components aligns with the European Fusion Roadmap and comprises the characterization and qualification of the in-vessel baseline materials EUROFER97, CuCrZr and tungsten, advanced structural and high heat flux materials developed for risk mitigation, as well as optical and dielectric fun…
Preprint PublishedJ. -Ch. Sublet I.P. Bondarenko G. Bonny J.L. Conlin M.R. Gilbert L.R. Greenwood P.J. Griffin P. Helgesson Y. Iwamoto V. A. Khryachkov T. A. Khromyleva A. Yu. Konobeyev N. Lazarev L. Luneville F. Mota C. J. Ortiz D. Rochman S. P. Simakov D. Simeone H. Sjostrand D. Terentyev R. Vila
Nuclear interactions can be the source of atomic displacement and post-short-term cascade annealing defects in irradiated structural materials. Such quantities are derived from, or can be correlated to, nuclear kinematic simulations of primary atomic energy distributions spectra and the quantification of the numbers of secondary defects produced pe…
Published