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Journal Article (234)
1.
Journal Article
26, 100943 (2021)
Hydrogen content in divertor baffle tiles in Wendelstein 7-X. Nuclear Materials and Energy 2.
Journal Article
61, 016025 (2021)
Quantification of erosion pattern using picosecond-LIBS on a vertical divertor target element exposed in W7-X. Nuclear Fusion 3.
Journal Article
23, 100749 (2020)
Impact of surface enrichment and morphology on sputtering of EUROFER by deuterium. Nuclear Materials and Energy 4.
Journal Article
2020 (T171), 014033 (2020)
Inspection of W 7-X plasma-facing components after the operation phase OP1.2b: observations and first assessments. Physica Scripta 5.
Journal Article
2020 (T171), 014059 (2020)
Comparison of erosion and deposition in JET divertor during the first three ITER-like wall campaigns. Physica Scripta 6.
Journal Article
2020 (T171), 014035 (2020)
Material erosion and deposition on the divertor of W7-X. Physica Scripta 7.
Journal Article
60, 025001 (2020)
Ion beam analysis of fusion plasma-facing materials and components: facilities and research challenges. Nuclear Fusion 8.
Journal Article
468, pp. 37 - 47 (2020)
International Atomic Energy Agency inter-comparison of particle induced gamma-ray emission codes for bulk samples. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms 9.
Journal Article
25, 100821 (2020)
Integrated modelling: Coupling of surface evolution and plasma-impurity transport. Nuclear Materials and Energy 10.
Journal Article
2020 (T171), 014040 (2020)
Impurity sources and fluxes in W7-X: from the plasma-facing components to the edge layer. Physica Scripta 11.
Journal Article
60, 096002 (2020)
Deuterium retention in tungsten irradiated by different ions. Nuclear Fusion 12.
Journal Article
532, 147185 (2020)
3-Dimensional analysis of layer structured samples with high depth resolution using picosecond laser-induced breakdown spectroscopy. Applied Surface Science 13.
Journal Article
2020 (T171), 014018 (2020)
Ex situ analysis of W7-X divertor plasma-facing components by picosecond laser diagnostics. Physica Scripta 14.
Journal Article
60, 126005 (2020)
Deuterium retention in mixed Be-W-D codeposited layers. Nuclear Fusion 15.
Journal Article
23, 100747 (2020)
High temperature recovery of radiation defects in tungsten and its effect on deuterium retention. Nuclear Materials and Energy 16.
Journal Article
531, 152017 (2020)
Vacancy cluster growth and thermal recovery in hydrogen-irradiated tungsten. Journal of Nuclear Materials 17.
Journal Article
14, C10012 (2019)
Validating the ASCOT modelling of NBI fast ions in Wendelstein 7-X stellarator. Journal of Instrumentation 18.
Journal Article
59, 096035 (2019)
Erosion, screening, and migration of tungsten in the JET divertor. Nuclear Fusion 19.
Journal Article
138, pp. 78 - 108 (2019)
Material migration and fuel retention studies during the JET carbon divertor campaigns. Fusion Engineering and Design 20.
Journal Article
146, Pt. A, pp. 242 - 245 (2019)
Erosion and deposition investigations on Wendelstein 7-X first wall components for the first operation phase in divertor configuration. Fusion Engineering and Design