T. W. Morgan

Morbey, M., Gonzalez, J., Arnold Bik, W., Tyburska-Pueschel, B., & Morgan, T. W. (2024). Deuterium retention in co-deposition with lithium in Magnum-PSI: experimental analysis and comparison with SOLPS-ITER. Nuclear Fusion, 64(7), 076019. https://doi.org/10.1088/1741-4326/ad4614

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. W., 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. W. (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. W., & 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. W. (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., Alonso van der Westen, S., Brons, S., Classen, I. J., van Dommelen, J. W., … Morgan, T. W. (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)