Publications of R. Neu
All genres
Journal Article (347)
2024
Journal Article
38, 101591 (2024)
Progress in the development of industrial scale tungsten fibre-reinforced composite materials. Nuclear Materials and Energy
Journal Article
52 (9), pp. 4167 - 4173 (2024)
Armor Thickness Assessment for the Divertor Tokamak Test Facility (DTT) Divertor Targets. IEEE Transactions on Plasma Science
Journal Article
64, 112015 (2024)
Divertor Tokamak Test facility project: status of design and implementation. Nuclear Fusion
Journal Article
313, 02002 (2024)
Appearance and analysis of a reflecting coating damage. EPJ Web of Conferences
Journal Article
64, 112008 (2024)
Recent progress of JT-60SA project toward plasma operation. Nuclear Fusion
Journal Article
125, 106864 (2024)
Influence of laser beam shaping on the cracking behavior of tungsten at single weld lines. International Journal of Refractory Metals and Hard Materials
Journal Article
64, 112001 (2024)
Overview of ASDEX upgrade results in view of ITER and DEMO. Nuclear Fusion 2023
Journal Article
192, 113629 (2023)
Conceptual design of the next generation of W7-X divertor W-target elements. Fusion Engineering and Design
Journal Article
191, 113742 (2023)
Pre-conceptual design of a PFC equipped with a W lattice armour for first wall limiters in the EU-DEMO fusion reactor. Fusion Engineering and Design
Journal Article
37, 101506 (2023)
Tungsten based divertor development for Wendelstein 7-X. Nuclear Materials and Energy
Journal Article
103 (11), pp. 1029 - 1047 (2023)
Rate-controlling deformation mechanisms in drawn tungsten wires. Philosophical Magazine
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
Journal Article
10, 116516 (2023)
Material and component developments for the DEMO divertor using fibre reinforcement and additive manufacturing. Materials Research Express
Journal Article
34, 101343 (2023)
Investigations on cold spray tungsten/tantalum coatings for plasma facing applications. Nuclear Materials and Energy
Journal Article
34, 101320 (2023)
Surface features of strongly heated bulk tungsten divertor plates at ASDEX Upgrade. Nuclear Materials and Energy
Journal Article
37, 101528 (2023)
Design and GLADIS testing of a liquid tin divertor module prior to exposure in ASDEX Upgrade. Nuclear Materials and Energy
Journal Article
192, 113604 (2023)
Parametric FE model for the thermal and hydraulic optimization of a Plasma Facing Component equipped with sacrificial lattice armours for First Wall limiter application in EU-DEMO fusion reactor. Fusion Engineering and Design 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
311, 131526 (2022)
Charpy impact tests of tungsten fiber–reinforced composite from -150°C to 1000°C. Materials Letters
Journal Article
33, 101276 (2022)
Design of a multi-configurations divertor for the DTT facility. Nuclear Materials and Energy