Publications of C. P. Dhard
All genres
Journal Article (48)
2024
Journal Article
38, 101585 (2024)
Exposure of tungsten heavy alloys at high thermal loads in LHD. Nuclear Materials and Energy 2023
Journal Article
191, 113589 (2023)
Erosion and redeposition pattern on the W7-X graphite test divertor unit tile. Fusion Engineering and Design
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
Journal Article
34, 101352 (2023)
Assessment of carbon net erosion/deposition at the divertor of W7-X. Nuclear Materials and Energy
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 2022
Journal Article
62, 016006 (2022)
Plasma-surface interaction in the stellarator W7-X: conclusions drawn from operation with graphite plasma-facing components. Nuclear Fusion
Journal Article
33, 101274 (2022)
Observation of non-thermal electrons outside the SOL in the Wendelstein 7-X stellarator. Nuclear Materials and Energy
Journal Article
62, 126049 (2022)
Carbon erosion/deposition on the divertor of W7-X during the operational period OP 1.2b. Nuclear Fusion
Journal Article
62, 042022 (2022)
Experimental confirmation of efficient island divertor operation and successful neoclassical transport optimization in Wendelstein 7-X. Nuclear Fusion
Journal Article
97, 024005 (2022)
Investigation of boron distribution and material migration on the W7-X divertor by picosecond LIBS. Physica Scripta
Journal Article
62, 106023 (2022)
Distributions of deposits and hydrogen on the upper and lower TDUs3 target elements of Wendelstein 7-X. Nuclear Fusion 2021
Journal Article
96, 124059 (2021)
Plasma-wall interaction studies in W7-X: main results from the recent divertor operations. Physica Scripta
Journal Article
61, 106003 (2021)
Overview of the results from divertor experiments with attached and detached plasmas at Wendelstein 7-X and their implications for steady-state operation. Nuclear Fusion
Journal Article
96, 124070 (2021)
Erosion of tungsten marker layers in W7-X. Physica Scripta
Journal Article
26, 100943 (2021)
Hydrogen content in divertor baffle tiles in Wendelstein 7-X. Nuclear Materials and Energy
Journal Article
96, 124023 (2021)
Deposition of 13C tracer and impurity elements on the divertor of Wendelstein 7-X. Physica Scripta
Journal Article
61, 016025 (2021)
Quantification of erosion pattern using picosecond-LIBS on a vertical divertor target element exposed in W7-X. Nuclear Fusion 2020
Journal Article
2020 (T171), 014033 (2020)
Inspection of W 7-X plasma-facing components after the operation phase OP1.2b: observations and first assessments. Physica Scripta
Journal Article
60, 096012 (2020)
Understanding baffle overloads observed in high-mirror configuration on Wendelstein 7-X. Nuclear Fusion
Journal Article
15, 2402012 (2020)
Inspection of Arc Trails Formed in Stellarator/Heliotron Devices W7-X and LHD. Plasma and Fusion Research