DIFFER

T. W. Morgan

First name
T.
Middle name
W.
Last name
Morgan
ORCID
0000-0002-5066-015X
Andruczyk, D., Rizkallah, R., O’Dea, D., Shone, A., Smith, S., Kamiyama, B., … Smolentsev, S. (2023). Overview of Liquid-Metal PFC R&D at the University of Illinois Urbana-Champaign. Fusion Science and Technology, 79(8), 1099-1112. https://doi.org/10.1080/15361055.2023.2171259 (Original work published 2023)
Gonzalez, J., Westerhof, E., & Morgan, T. W. (2023). SOLPS-ITER simulations of a vapour box design for the linear device Magnum-PSI. Plasma Physics and Controlled Fusion, 65(5), 055021. https://doi.org/10.1088/1361-6587/acc8fa
Oyarzabal, E., Tabares, F. L., Liniers, M., Alegre, D., Tafalla, D., McCarthy, K. J., … team, O. (2023). Comparative study of different Sn wetted W CPSs exposed to NBI fluxes in the OLMAT facility. Fusion Engineering and Design, 190, 113711. https://doi.org/10.1016/j.fusengdes.2023.113711 (Original work published 2023)
Herashchenko, S. S., Makhlai, V., Garkusha, I. E., Petrov, Y. V., Aksenov, N. N., Byrka, O. V., … Morgan, T. W. (2023). The CPS’s pre-heating effect on the capability to withstand extreme plasma loads. Fusion Engineering and Design, 190, 113527. https://doi.org/10.1016/j.fusengdes.2023.113527 (Original work published 2023)
Scholte, J. G., Iafrati, M., Lam, S. S., Tyburska-Pueschel, B., Riepen, M., Brochard, F., … Morgan, T. W. (2023). Reducing tin droplet ejection from capillary porous structures under hydrogen plasma exposure in Magnum-PSI. Nuclear Materials and Energy, 34, 101315. https://doi.org/10.1016/j.nme.2022.101315 (Original work published 2023)
Onwudinanti, C., Pols, M., Brocks, G., Koelman, J. M. V. A., van Duin, A. T., Morgan, T. W., & Tao, S. (2022). A ReaxFF molecular dynamics study of hydrogen diffusion in ruthenium - the role of grain boundaries. Journal of Physical Chemistry C, 126(13), 5950-5959. https://doi.org/10.1021/acs.jpcc.1c08776 (Original work published 2022)
Pereira, V. S. M., Wang, S., Morgan, T. W., Schut, H., & Sietsma, J. (2022). Microstructural evolution and behaviour of deuterium in a ferritic ODS 12 Cr steel annealed at different temperatures. Metallurgical and Materials Transactions A, 53(3), 874–892. https://doi.org/10.1007/s11661-021-06559-0
Ou, W., Rindt, P., Li, K., Arnold Bik, W., & Morgan, T. W. (2022). Deuterium retention and removal in liquid lithium determined by in-situ NRA in Magnum-PSI. Nuclear Fusion, 62(7), 076010. https://doi.org/10.1088/1741-4326/ac3295
Li, Y., Vermeij, T., Hoefnagels, J. P. M., Zhu, Q., & Morgan, T. W. (2022). Influence of porosity and blistering on the thermal fatigue behavior of tungsten. Nuclear Fusion, 62(7), 076039. https://doi.org/10.1088/1741-4326/ac6a65
Hayashi, Y., Tanaka, H., Ohno, N., Kajita, S., Morgan, T. W., van der Meiden, H. J., … Masuda, S. (2022). Reduction of pulsed particle load with dynamic pressure induced by transient recycled neutral flux. Plasma Physics and Controlled Fusion, 64(10), 105013. https://doi.org/10.1088/1361-6587/ac8acb