Publikationen von D. Naujoks
Alle Typen
Zeitschriftenartikel (111)
1.
Zeitschriftenartikel
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.
Zeitschriftenartikel
: 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.
Zeitschriftenartikel
38, 101585 (2024)
Exposure of tungsten heavy alloys at high thermal loads in LHD. Nuclear Materials and Energy 4.
Zeitschriftenartikel
: Conditions and benefits of X-point radiation for the island divertor. Nuclear Fusion 64, 086027 (2024)
5.
Zeitschriftenartikel
: Heat and particle exhaust in high-performance plasmas in Wendelstein 7-X. Nuclear Fusion 64, 076060 (2024)
6.
Zeitschriftenartikel
: Overview of the first Wendelstein 7-X long pulse campaign with fully water-cooled plasma facing components. Nuclear Fusion 64, 112002 (2024)
7.
Zeitschriftenartikel
: First operation and validation of simulations for the divertor cryo-vacuum pump in Wendelstein 7-X. Fusion Engineering and Design 208, 114671 (2024)
8.
Zeitschriftenartikel
52 (9), S. 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.
Zeitschriftenartikel
: 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.
Zeitschriftenartikel
: 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.
Zeitschriftenartikel
: Properties of boron layers deposited during boronisations in W7-X. Nuclear Materials and Energy 41, 101778 (2024)
12.
Zeitschriftenartikel
64, 076011 (2024)
Numerical simulation of neutral gas dynamics in the W7-X sub-divertor. Nuclear Fusion 13.
Zeitschriftenartikel
: Conceptual design of the next generation of W7-X divertor W-target elements. Fusion Engineering and Design 192, 113629 (2023)
14.
Zeitschriftenartikel
: Tungsten based divertor development for Wendelstein 7-X. Nuclear Materials and Energy 37, 101506 (2023)
15.
Zeitschriftenartikel
191, 113589 (2023)
Erosion and redeposition pattern on the W7-X graphite test divertor unit tile. Fusion Engineering and Design 16.
Zeitschriftenartikel
: 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.
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 18.
Zeitschriftenartikel
34, 101352 (2023)
Assessment of carbon net erosion/deposition at the divertor of W7-X. Nuclear Materials and Energy 19.
Zeitschriftenartikel
: 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.
Zeitschriftenartikel
: Corrigendum: Gas exhaust in the Wendelstein 7-X stellarator during the first divertor operation (2022 Nucl. Fusion 62 096016). Nuclear Fusion 63, 099501 (2023)