An overview of all scientific publications of the Max Planck Institute for Plasma Physics.
Journal Article (13218)
821.
Journal Article
65, 075008 (2023)
Predictive simulations of NBI ion power load to the ICRH antenna in Wendelstein 7-X. Plasma Physics and Controlled Fusion 822.
Journal Article
65, 085009 (2023)
SOLPS-ITER modeling of EU-DEMO Ar-seeded cases with drifts and kinetic neutrals. Plasma Physics and Controlled Fusion 823.
Journal Article
63, 106002 (2023)
ICRF plasma production at hydrogen minority regime in LHD. Nuclear Fusion 824.
Journal Article
18, 2402042 (2023)
ICRF Plasma Production with Hydrogen Minority Heating in Uragan-2M and Large Helical Device. Plasma and Fusion Research 825.
Journal Article
194, 113887 (2023)
ICRF plasma production in gas mixtures in the Uragan-2M stellarator. Fusion Engineering and Design 826.
Journal Article
Non-resonant microwave discharge strat-up in Heliotron J. Voprosy Atomnoj Nauki i Techniki = Problems of Atomic Science and Technology (1 (143)), pp. 3 - 8 (2023)
827.
Journal Article
35, 101406 (2023)
Deuterium plasma exposure of thin oxide films on tungsten – oxygen removal and deuterium uptake. Nuclear Materials and Energy 828.
Journal Article
63, 066021 (2023)
Investigation of ELM-related Larmor ion flux into toroidal gaps of divertor target plates. Nuclear Fusion 829.
Journal Article
34, 101374 (2023)
Wall conditioning effects and boron migration during boron powder injection in ASDEX Upgrade. Nuclear Materials and Energy 830.
Journal Article
192, 113828 (2023)
Short-pulse frequency stabilization of a MW-class ECRH gyrotron at W7-X for CTS diagnostic. Fusion Engineering and Design 831.
Journal Article
63, 026022 (2023)
Effects of drifts on scrape-off layer transport in W7-X. Nuclear Fusion 832.
Journal Article
65, 015013 (2023)
Linear scattering theory of short-pulse reflectometry. Plasma Physics and Controlled Fusion 833.
Journal Article
34, 101363 (2023)
First feedback-controlled divertor detachment in W7-X: Experience from TDU operation and prospects for operation with actively cooled divertor. Nuclear Materials and Energy 834.
Journal Article
94, 053503 (2023)
Layer thickness characterization of Faraday cup fast ion loss detectors. Review of Scientific Instruments 835.
Journal Article
196, 114020 (2023)
Admixed pellets for fast and efficient delivery of plasma enhancement gases: Investigations at AUG exploring the option for EU-DEMO. Fusion Engineering and Design 836.
Journal Article
194, 113917 (2023)
Systems engineering procedure for requirements management of divertor system of tokamak reactors. Fusion Engineering and Design 837.
Journal Article
277, 04003 (2023)
The ECRH-Power Upgrade at the Wendelstein 7-X Stellarator. EPJ Web of Conferences 838.
Journal Article
4 (2), pp. 375 - 390 (2023)
Bulk Tungsten Fiber-Reinforced Tungsten (Wf/W) Composites Using Yarn-Based Textile Preforms. Journal of Nuclear Engineering 839.
Journal Article
56, 085202 (2023)
RF efficiency measurements of inductively-coupled plasma H- ion sources at accelerator facilities. Journal of Physics D: Applied Physics 840.
Journal Article
63, 096012 (2023)
Gyro orbit simulations of neutral beam injection in Wendelstein 7-X. Nuclear Fusion