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
: 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 66, 015005 (2024)
3.
Journal Article
38, 101585 (2024)
Exposure of tungsten heavy alloys at high thermal loads in LHD. Nuclear Materials and Energy 4.
Journal Article
: Conditions and benefits of X-point radiation for the island divertor. Nuclear Fusion 64, 086027 (2024)
5.
Journal Article
: Heat and particle exhaust in high-performance plasmas in Wendelstein 7-X. Nuclear Fusion 64, 076060 (2024)
6.
Journal Article
: Overview of the first Wendelstein 7-X long pulse campaign with fully water-cooled plasma facing components. Nuclear Fusion 64, 112002 (2024)
7.
Journal Article
: First operation and validation of simulations for the divertor cryo-vacuum pump in Wendelstein 7-X. Fusion Engineering and Design 208, 114671 (2024)
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
: Overview of Large Helical Device experiments of basic plasma physics for solving crucial issues in reaching burning plasma conditions. Nuclear Fusion 64, 112009 (2024)
10.
Journal Article
: Migration and balance of 13C in the stellarator Wendelstein 7-X after 13CH4 local injection into the island divertor. Nuclear Materials and Energy 39, 101675 (2024)
11.
Journal Article
: Properties of boron layers deposited during boronisations in W7-X. Nuclear Materials and Energy 41, 101778 (2024)
12.
Journal Article
64, 076011 (2024)
Numerical simulation of neutral gas dynamics in the W7-X sub-divertor. Nuclear Fusion 13.
Journal Article
: Conceptual design of the next generation of W7-X divertor W-target elements. Fusion Engineering and Design 192, 113629 (2023)
14.
Journal Article
: Tungsten based divertor development for Wendelstein 7-X. Nuclear Materials and Energy 37, 101506 (2023)
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
: Improvement in the simulation tools for heat distribution predictions and control of baffle and middle divertor loads in Wendelstein 7-X. Nuclear Fusion 63, 026031 (2023)
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
: Performance of tungsten plasma facing components in the stellarator experiment W7-X: Recent results from the first OP2 campaign. Nuclear Materials and Energy 37, 101514 (2023)
20.
Journal Article
: Corrigendum: Gas exhaust in the Wendelstein 7-X stellarator during the first divertor operation (2022 Nucl. Fusion 62 096016). Nuclear Fusion 63, 099501 (2023)