Publications of D. Naujoks
All genres
Journal Article (111)
1.
Journal Article
42, 101846 (2025)
In-vessel inspection of arc traces on the W7-X plasma facing components after the operation phase OP2.1. Nuclear Materials and Energy 2.
Journal Article
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 3.
Journal Article
38, 101585 (2024)
Exposure of tungsten heavy alloys at high thermal loads in LHD. Nuclear Materials and Energy 4.
Journal Article
64, 086027 (2024)
Conditions and benefits of X-point radiation for the island divertor. Nuclear Fusion 5.
Journal Article
64, 076060 (2024)
Heat and particle exhaust in high-performance plasmas in Wendelstein 7-X. Nuclear Fusion 6.
Journal Article
64, 112002 (2024)
Overview of the first Wendelstein 7-X long pulse campaign with fully water-cooled plasma facing components. Nuclear Fusion 7.
Journal Article
208, 114671 (2024)
First operation and validation of simulations for the divertor cryo-vacuum pump in Wendelstein 7-X. Fusion Engineering and Design 8.
Journal Article
52 (9), pp. 3511 - 3515 (2024)
Performance of LaB6-Emitters for Neutral Gas Pressure Gauges During Plasma Operation in the Large Helical Device. IEEE Transactions on Plasma Science 9.
Journal Article
64, 112009 (2024)
Overview of Large Helical Device experiments of basic plasma physics for solving crucial issues in reaching burning plasma conditions. Nuclear Fusion 10.
Journal Article
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 11.
Journal Article
41, 101778 (2024)
Properties of boron layers deposited during boronisations in W7-X. Nuclear Materials and Energy 12.
Journal Article
64, 076011 (2024)
Numerical simulation of neutral gas dynamics in the W7-X sub-divertor. Nuclear Fusion 13.
Journal Article
192, 113629 (2023)
Conceptual design of the next generation of W7-X divertor W-target elements. Fusion Engineering and Design 14.
Journal Article
37, 101506 (2023)
Tungsten based divertor development for Wendelstein 7-X. Nuclear Materials and Energy 15.
Journal Article
191, 113589 (2023)
Erosion and redeposition pattern on the W7-X graphite test divertor unit tile. Fusion Engineering and Design 16.
Journal Article
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 17.
Journal Article
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 18.
Journal Article
34, 101352 (2023)
Assessment of carbon net erosion/deposition at the divertor of W7-X. Nuclear Materials and Energy 19.
Journal Article
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 20.
Journal Article
63, 099501 (2023)
Corrigendum: Gas exhaust in the Wendelstein 7-X stellarator during the first divertor operation (2022 Nucl. Fusion 62 096016). Nuclear Fusion