DIFFER

T.W. Morgan

First name
T.W.
Last name
Morgan
Li, K., Du, B., Li, Y., Wang, D., Liu, H., Zhou, H., et al. (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)
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Terentyev, D., Wirtz, M., Morgan, T. W., Nozawa, T., Zinovev, A., Chang, C. C., et al. (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)
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Wang, S. C., 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)
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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)
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Li, Y., Hou, J., Shah, V., Huang, Y., van Dommelen, J. A. W., Lu, W. J., et al. (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)
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Scholte, J. G. A., Balden, M., Brida, D., Cecrdle, J., Dux, R., Elgeti, S., et al. (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)
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Scholte, J. G. A., Balden, M., Böswirth, B., Elgeti, S., Greuner, H., Herrmann, A., et al. (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)
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de Castro, A., Oyarzabal, E., Alegre, D., Tafalla, D., Gonzalez, M., McCarthy, P. J., et al. (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)
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Tanke, V. F. B., Al, R. S., van der Westen, A., Brons, S., Classen, I. G. J., van Dommelen, J. A. W., et al. (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)
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Hirooka, Y., de Castro, A., Goto, T., Maingi, R., Morgan, T. W., 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
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