Publikationen von R. Arredondo Parra
Alle Typen
Zeitschriftenartikel (22)
21.
Zeitschriftenartikel
57, 016030 (2017)
Impact of lithium pellets on plasma performance in the ASDEX Upgrade all-metal-wall tokamak. Nuclear Fusion 22.
Zeitschriftenartikel
87, 023508 (2016)
A compact lithium pellet injector for tokamak pedestal studies in ASDEX Upgrade. Review of Scientific Instruments Konferenzbeitrag (1)
23.
Konferenzbeitrag
Impact of Lithium pellets on the plasma performance in the all-metal-wall tokamak ASDEX Upgrade. In: 43rd EPS Conference on Plasma Physics, P1.021 (Hg. Mantica, P.). 43rd EPS Conference on Plasma Physics, Leuven, 04. Juli 2016 - 08. Juli 2016. European Physical Society, Geneva (2016)
Vortrag (13)
24.
Vortrag
Ion-driven Permeation Experiments and Modelling. IAEA Technical Meeting on Nuclear Fusion Fuel Permeation in Reactor First Wall Components, Vienna, Virtual (eingereicht)
25.
Vortrag
Radiation damaging of tungsten: Recent advances in predicting tritium retention and transport for DEMO. 25th International Conference on Plasma Surface Interaction in Controlled Fusion Devices (PSI 25), Jeju (eingereicht)
26.
Vortrag
Self-consistent dynamic sputtering- and erosion simulations with SDTrimSP-3D. 25th International Conference on Ion Beam Analysis (IBA 2021) & 17th International Conference on Particle Induce X-ray Emission (PIXE) & International Conference on Secondary Ion Mass Spectrometry (SIMS), Virtual (eingereicht)
27.
Vortrag
Saturation of defect densities in displacement-damaged tungsten. 18th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-18), Virtual (eingereicht)
28.
Vortrag
Dynamic SDTrimSP-3D Simulations and Validation Experiments. 17th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-17), Eindhoven (eingereicht)
29.
Vortrag
Sputtering of EUROFER: The Role of Roughness. 3rd Research Coordination Meeting of CRP on "Plasma-wall Interaction with Reduced-activation Steel Surfaces in Fusion Devices (2015-2020)", Vienna (eingereicht)
30.
Vortrag
Bayesian determination of parameters for plasma-wall interactions. 39th International Workshop on Bayesian Inference and Maximum Entropy Methods in Science and Engineering (MaxEnt 2019), Garching (2019)
31.
Vortrag
Challenges and Approaches for Validated Plasma Modelling: A Case Study in Plasma-Wall-Interaction. 3rd IAEA Technical Meeting on Fusion Data Processing, Validation and Analysis, Vienna (2019)
32.
Vortrag
Plasma-Surface Interaction of RAFM Steels. 2018 ANS Winter Meeting and Nuclear Technology Expo. The
Technology of Fusion Energy (TOFE 2018), Orlando, FL (eingereicht)
33.
Vortrag
Bayesian determination of parameters for plasma-wall interactions. 38th International Workshop on Bayesian Inference and Maximum Entropy Methods in Science and Engineering (MaxEnt 2018), London (eingereicht)
34.
Vortrag
Developments at IPP regarding sputtering of EUROFER. 2nd Research Coordination Meeting "Plasma-wall Interaction with Reduced-activation Steel Surfaces in Fusion Devices", Vienna (eingereicht)
35.
Vortrag
Sputter-erosion of Low-activation Steel. 8th Forum on New Materials (CIMTEC 2018), Perugia (eingereicht)
36.
Vortrag
Impact of Lithium on the plasma performance in the all-metal-wall tokamak ASDEX Upgrade. DPG-Frühjahrstagung der Sektion Atome, Moleküle, Quantenoptik und Plasmen (SAMOP), Hannover (eingereicht)
Poster (22)
37.
Poster
Does Hydrogen-Driven Segregation Exist in the Iron-Tungsten-System? The Nuclear Materials Conference (NuMat 2024), Singapore (eingereicht)
38.
Poster
Sputter yield of tungsten materials with strongly different microstructure. 15th International Symposium on Fusion Nuclear Technology (ISFNT-15), Las Palmas de Gran Canaria (eingereicht)
39.
Poster
Implications of T Loss in First Wall Armor and Structural Materials on T-Self-Sufficiency in Future Burning Fusion Devices. 29th IAEA Fusion Energy Conference (FEC 2023), London (eingereicht)
40.
Poster
Ion-driven permeation of deuterium in W/EUROFER layer systems at TAPAS. 20th International Conference on Fusion Reactor Materials (ICFRM-20), Virtual (eingereicht)