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Plasma Material Interactions Publications
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Plasma Material Interactions Publications
Displaying 11 - 20 of 308
2024
J. Hargreaves, H.E. Tipping, S. Moore, D. Kumar, D.J. Harding, H. Dominguez-Andrade, C. Bell, P.D. Hanna, H. Dawson, T.L. Martin ,
The transient thermal ageing of Eurofer 97 by mitigated plasma disruptions
, Materials and Design
, 244 (2024) 113207
,
,
DOI
M. Morbey, J. Gonzalez, W. Arnold Bik, B. Tyburska-Pueschel, T. W. Morgan ,
Deuterium retention in co-deposition with lithium in Magnum-PSI: experimental analysis and comparison with SOLPS-ITER
, Nuclear Fusion
, 64 (2024) 076019
,
,
DOI
K. Li, B. Du, Y. Li, D. Wang, H. Liu, H. Zhou, G. Luo, J. Yao, T. W. Morgan, W. Liu , et al. ,
Blistering and retention behavior of laser powder bed fused tungsten alloys under hydrogen plasma irradiation
, Journal of Nuclear Materials
, 595 (2024) 155049
, Short communication (07/2024)
,
DOI
D. Terentyev, M. Wirtz, T. W. Morgan, T. Nozawa, A. Zinovev, C.C. Chang, K. Poleshchuk, J. Elenbaas ,
Comparative study of ITER conform tungsten grades exposed to high heat flux and neutron irradiation damage
, Fusion Engineering and Design
, 200 (2024) 114200
,
DOI
2023
S.C. Wang, M. van Kampen, T. W. Morgan ,
Promotion of plasma-induced deuterium uptake of ruthenium films by monolayer-thick tin layers
, ACS Applied Materials and Interfaces
, 15 (2023) 57769–57782
,
,
2023_5760.pdf
,
DOI
E. Yildirim, P. Mummery, T. W. Morgan, E. Jimenez-Melero ,
Delayed surface degradation in W-Ta alloys at 400° C under high-fluence 40 eV He plasma exposure
, Fusion Engineering and Design
, 197 (2023) 114061
,
,
DOI
Y. Li, J. Hou, V. Shah, Y. Huang, J.A. W. van Dommelen, W.J. Lu, Q. Zhu, T. W. Morgan ,
Amorphous and anisotropic surface relief formation in tungsten under repeated high-flux hydrogen plasma loads
, Nuclear Materials and Energy
, 37 (2023) 101544
,
,
DOI
J.G. A. Scholte, M. Balden, D. Brida, J. Cecrdle, R. Dux, S. Elgeti, M. Faitsch, A. Herrmann, J. Horáček, T. W. Morgan , et al. ,
Performance of a liquid Sn divertor target during ASDEX Upgrade L-mode and H-mode operation
, Nuclear Materials and Energy
, 37 (2023) 101522
,
,
DOI
J.G. A. Scholte, M. Balden, B. Böswirth, S. Elgeti, H. Greuner, A. Herrmann, K. Hunger, K. Krieger, R.C. van Schaik, T. W. Morgan , et al. ,
Design and GLADIS testing of a liquid tin divertor module prior to exposure in ASDEX Upgrade
, Nuclear Materials and Energy
, 37 (2023) 101528
,
,
DOI
A. de Castro, E. Oyarzabal, D. Alegre, D. Tafalla, M. Gonzalez, P.J. McCarthy, J.G. A. Scholte, T. W. Morgan, F.L. Tabares, OLMAT team ,
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 (2023) 45
,
,
DOI
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