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Zeitschriftenartikel (232)
1.
Zeitschriftenartikel
61, 016025 (2021)
Quantification of erosion pattern using picosecond-LIBS on a vertical divertor target element exposed in W7-X. Nuclear Fusion 2.
Zeitschriftenartikel
23, 100749 (2020)
Impact of surface enrichment and morphology on sputtering of EUROFER by deuterium. Nuclear Materials and Energy 3.
Zeitschriftenartikel
2020 (T171), 014033 (2020)
Inspection of W 7-X plasma-facing components after the operation phase OP1.2b: observations and first assessments. Physica Scripta 4.
Zeitschriftenartikel
2020 (T171), 014059 (2020)
Comparison of erosion and deposition in JET divertor during the first three ITER-like wall campaigns. Physica Scripta 5.
Zeitschriftenartikel
60, 025001 (2020)
Ion beam analysis of fusion plasma-facing materials and components: facilities and research challenges. Nuclear Fusion 6.
Zeitschriftenartikel
2020 (T171), 014035 (2020)
Material erosion and deposition on the divertor of W7-X. Physica Scripta 7.
Zeitschriftenartikel
468, S. 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 8.
Zeitschriftenartikel
2020 (T171), 014040 (2020)
Impurity sources and fluxes in W7-X: from the plasma-facing components to the edge layer. Physica Scripta 9.
Zeitschriftenartikel
60, 096002 (2020)
Deuterium retention in tungsten irradiated by different ions. Nuclear Fusion 10.
Zeitschriftenartikel
532, 147185 (2020)
3-Dimensional analysis of layer structured samples with high depth resolution using picosecond laser-induced breakdown spectroscopy. Applied Surface Science 11.
Zeitschriftenartikel
2020 (T171), 014018 (2020)
Ex situ analysis of W7-X divertor plasma-facing components by picosecond laser diagnostics. Physica Scripta 12.
Zeitschriftenartikel
60, 126005 (2020)
Deuterium retention in mixed Be-W-D codeposited layers. Nuclear Fusion 13.
Zeitschriftenartikel
23, 100747 (2020)
High temperature recovery of radiation defects in tungsten and its effect on deuterium retention. Nuclear Materials and Energy 14.
Zeitschriftenartikel
531, 152017 (2020)
Vacancy cluster growth and thermal recovery in hydrogen-irradiated tungsten. Journal of Nuclear Materials 15.
Zeitschriftenartikel
14, C10012 (2019)
Validating the ASCOT modelling of NBI fast ions in Wendelstein 7-X stellarator. Journal of Instrumentation 16.
Zeitschriftenartikel
59, 096035 (2019)
Erosion, screening, and migration of tungsten in the JET divertor. Nuclear Fusion 17.
Zeitschriftenartikel
138, S. 78 - 108 (2019)
Material migration and fuel retention studies during the JET carbon divertor campaigns. Fusion Engineering and Design 18.
Zeitschriftenartikel
146, Pt. A, S. 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 19.
Zeitschriftenartikel
59, 112021 (2019)
Overview of the JET preparation for deuterium-tritium operation with the ITER like-wall. Nuclear Fusion 20.
Zeitschriftenartikel
59, 112004 (2019)
Overview of first Wendelstein 7-X high-performance operation. Nuclear Fusion