T.W. Morgan

Li, K. ., Du, B. ., Li, Y. ., Wang, D. ., Liu, H. ., Zhou, H. ., … Chen, W. . (2024). Blistering and retention behavior of laser powder bed fused tungsten alloys under hydrogen plasma irradiation. Journal of Nuclear Materials, 595, 155049. https://doi.org/10.1016/j.jnucmat.2024.155049 (Original work published 2024)

Terentyev, D. ., Wirtz, M. ., Morgan, T. ., Nozawa, T. ., Zinovev, A. ., Chang, C. ., … Elenbaas, J. . (2024). Comparative study of ITER conform tungsten grades exposed to high heat flux and neutron irradiation damage. Fusion Engineering and Design, 200, 114200. https://doi.org/10.1016/j.fusengdes.2024.114200 (Original work published 2024)

Wang, S. ., van Kampen, M. ., & Morgan, T. . (2023). Promotion of plasma-induced deuterium uptake of ruthenium films by monolayer-thick tin layers. ACS Applied Materials and Interfaces, 15(49), 57769–57782. https://doi.org/10.1021/acsami.3c11245 (Original work published 2023)

Yildirim, E. ., Mummery, P. ., Morgan, T. ., & Jimenez-Melero, E. . (2023). Delayed surface degradation in W-Ta alloys at 400° C under high-fluence 40 eV He plasma exposure. Fusion Engineering and Design, 197, 114061. https://doi.org/10.1016/j.fusengdes.2023.114061 (Original work published 2023)

Li, Y. ., Hou, J. ., Shah, V. ., Huang, Y. ., van Dommelen, J. W., Lu, W. ., … Morgan, T. . (2023). Amorphous and anisotropic surface relief formation in tungsten under repeated high-flux hydrogen plasma loads. Nuclear Materials and Energy, 37, 101544. https://doi.org/10.1016/j.nme.2023.101544 (Original work published 2023)

Scholte, J. A., Balden, M. ., Brida, D. ., Cecrdle, J. ., Dux, R. ., Elgeti, S. ., … Team, A. U. (2023). Performance of a liquid Sn divertor target during ASDEX Upgrade L-mode and H-mode operation. Nuclear Materials and Energy, 37, 101522. https://doi.org/10.1016/j.nme.2023.101522 (Original work published 2023)

Scholte, J. A., Balden, M. ., Böswirth, B. ., Elgeti, S. ., Greuner, H. ., Herrmann, A. ., … Zammuto, I. . (2023). Design and GLADIS testing of a liquid tin divertor module prior to exposure in ASDEX Upgrade. Nuclear Materials and Energy, 37, 101528. https://doi.org/10.1016/j.nme.2023.101528 (Original work published 2023)

de Castro, A. ., Oyarzabal, E. ., Alegre, D. ., Tafalla, D. ., Gonzalez, M. ., McCarthy, P. ., … team, O. . (2023). Physics and Technology Research for Liquid-Metal Divertor Development, Focused on a Tin-Capillary Porous System Solution, at the OLMAT High Heat-Flux Facility. Journal of Fusion Energy, 42(2), 45. https://doi.org/10.1007/s10894-023-00373-9 (Original work published 2023)

Tanke, V. ., Al, R. ., van der Westen, A. ., Brons, S. ., Classen, I. J., van Dommelen, J. W., … Morgan, T. . (2023). LiMeS-Lab: An Integrated Laboratory for the Development of Liquid–Metal Shield Technologies for Fusion Reactors. Journal of Fusion Energy, 42(2), 44. https://doi.org/10.1007/s10894-023-00379-3 (Original work published 2023)

Hirooka, Y. ., de Castro, A. ., Goto, T. ., Maingi, R. ., Morgan, T. ., Ono, M. ., & Shimada, M. . (2023). Conference Report on the 7th International Symposium on Liquid metals Applications for fusion (ISLA-7). Nuclear Fusion, 63(9), 097001. https://doi.org/10.1088/1741-4326/ace6bd