Publikationen von D. Naujoks
Alle Typen
Zeitschriftenartikel (109)
1.
Zeitschriftenartikel
66, 015005 (2024)
Analysis of the neutral fluxes in the divertor region of Wendelstein 7-X under attached and detached conditions using EMC3-EIRENE. Plasma Physics and Controlled Fusion 2.
Zeitschriftenartikel
38, 101585 (2024)
Exposure of tungsten heavy alloys at high thermal loads in LHD. Nuclear Materials and Energy 3.
Zeitschriftenartikel
64, 086027 (2024)
Conditions and benefits of X-point radiation for the island divertor. Nuclear Fusion 4.
Zeitschriftenartikel
64, 076060 (2024)
Heat and particle exhaust in high-performance plasmas in Wendelstein 7-X. Nuclear Fusion 5.
Zeitschriftenartikel
64, 112002 (2024)
Overview of the first Wendelstein 7-X long pulse campaign with fully water-cooled plasma facing components. Nuclear Fusion 6.
Zeitschriftenartikel
208, 114671 (2024)
First operation and validation of simulations for the divertor cryo-vacuum pump in Wendelstein 7-X. Fusion Engineering and Design 7.
Zeitschriftenartikel
64, 112009 (2024)
Overview of Large Helical Device experiments of basic plasma physics for solving crucial issues in reaching burning plasma conditions. Nuclear Fusion 8.
Zeitschriftenartikel
39, 101675 (2024)
Migration and balance of 13C in the stellarator Wendelstein 7-X after 13CH4 local injection into the island divertor. Nuclear Materials and Energy 9.
Zeitschriftenartikel
41, 101778 (2024)
Properties of boron layers deposited during boronisations in W7-X. Nuclear Materials and Energy 10.
Zeitschriftenartikel
64, 076011 (2024)
Numerical simulation of neutral gas dynamics in the W7-X sub-divertor. Nuclear Fusion 11.
Zeitschriftenartikel
192, 113629 (2023)
Conceptual design of the next generation of W7-X divertor W-target elements. Fusion Engineering and Design 12.
Zeitschriftenartikel
37, 101506 (2023)
Tungsten based divertor development for Wendelstein 7-X. Nuclear Materials and Energy 13.
Zeitschriftenartikel
191, 113589 (2023)
Erosion and redeposition pattern on the W7-X graphite test divertor unit tile. Fusion Engineering and Design 14.
Zeitschriftenartikel
63, 026031 (2023)
Improvement in the simulation tools for heat distribution predictions and control of baffle and middle divertor loads in Wendelstein 7-X. Nuclear Fusion 15.
Zeitschriftenartikel
65, 055024 (2023)
Overview over the neutral gas pressures in Wendelstein 7-X during divertor operation under boronized wall conditions. Plasma Physics and Controlled Fusion 16.
Zeitschriftenartikel
34, 101352 (2023)
Assessment of carbon net erosion/deposition at the divertor of W7-X. Nuclear Materials and Energy 17.
Zeitschriftenartikel
37, 101514 (2023)
Performance of tungsten plasma facing components in the stellarator experiment W7-X: Recent results from the first OP2 campaign. Nuclear Materials and Energy 18.
Zeitschriftenartikel
63, 099501 (2023)
Corrigendum: Gas exhaust in the Wendelstein 7-X stellarator during the first divertor operation (2022 Nucl. Fusion 62 096016). Nuclear Fusion 19.
Zeitschriftenartikel
62, 016006 (2022)
Plasma-surface interaction in the stellarator W7-X: conclusions drawn from operation with graphite plasma-facing components. Nuclear Fusion 20.
Zeitschriftenartikel
33, 101274 (2022)
Observation of non-thermal electrons outside the SOL in the Wendelstein 7-X stellarator. Nuclear Materials and Energy