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Beiträge in referierten Zeitschriften 2021

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Self-passivating smart tungsten alloys for DEMO: a progress in joining and upscale for a first wall mockup
Tungsten 3, 101–115 () [10.1007/s42864-021-00079-5] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Design improvements, assembly and testing of the ICRH antenna for W7-X
Fusion engineering and design 166, 112205 - () [10.1016/j.fusengdes.2020.112205] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Three-dimensional first principles simulation of a hydrogen discharge
Plasma physics and controlled fusion 63(4), 045012 - () [10.1088/1361-6587/abdd75] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Hydrogen isotope permeation through yttria coatings on Eurofer in the diffusion limited regime
International journal of hydrogen energy 46(24), 13142 - 13149 () [10.1016/j.ijhydene.2021.01.072] Embargoed OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Monitoring Removal of W Layer from Ag Substrate Using Balmer-α Emission of Backscattered Hydrogen Atoms in Low Density Gas Discharge. Acta Physica Polonica A 138, 643 (2020), ERRATUM
Acta physica Polonica / A 139(2), 170 - 171 () [10.12693/APhysPolA.139.170] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Measurements of the energy distribution of W atoms sputtered by low energy Ar ions using high-resolution Doppler spectroscopy
Plasma physics and controlled fusion 63(1), 015008 () [10.1088/1361-6587/abc519] Embargoed OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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The upgraded TOMAS device: A toroidal plasma facility for wall conditioning, plasma production, and plasma–surface interaction studies
Review of scientific instruments 92(2), 023506 - () [10.1063/5.0033229] Embargoed OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Smart alloys as armor material for DEMO: Overview of properties and joining to structural materials
Fusion engineering and design 166, 112272 - () [10.1016/j.fusengdes.2021.112272] Embargoed OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Two-modes model of the non-equilibrium plasma chemical dissociation of CO 2
Plasma sources science and technology 30(5), 055003 - () [10.1088/1361-6595/abf368] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Main design features of the Rh-based first mirror developed for the ITER CXRS core diagnostics
Fusion engineering and design 169, 112408 - () [10.1016/j.fusengdes.2021.112408] Embargoed OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Exploring the Interface of Skin‐Layered Titanium Fibers for Electrochemical Water Splitting
Advanced energy materials 11(8), 2002926 () [10.1002/aenm.202002926] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Constructing a Multifunctional Interface between Membrane and Porous Transport Layer for Water Electrolyzers
ACS applied materials & interfaces 13(14), 16182 - 16196 () [10.1021/acsami.0c20690] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Nuclear analysis of the DEMO divertor survey visible high-resolution spectrometer
Fusion engineering and design 169, 112460 - () [10.1016/j.fusengdes.2021.112460] Embargoed OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Symmetries of 13C tracer deposition in EAST D and He plasmas investigated on the sub-mm to 100 mm scale by deuteron nuclear reaction analysis
Fusion engineering and design 166, 112292 - () [10.1016/j.fusengdes.2021.112292] Embargoed OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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A New High-Throughput Focused MeV Ion-Beam Analysis Setup
Instruments 5(1), 10 - () [10.3390/instruments5010010] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Analyses of deuterium retention in tungsten and graphite first wall materials by laser-induced ablation spectroscopy on EAST
Fusion engineering and design 162, 112108 - () [10.1016/j.fusengdes.2020.112108] Embargoed OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Hydrogen content in divertor baffle tiles in Wendelstein 7-X
Nuclear materials and energy 26, 100943 - () [10.1016/j.nme.2021.100943] DBCoverage  Download fulltext Files BibTeX | EndNote: XML, Text | RIS

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Determining Chemical Reaction Systems in Plasma-Assisted Conversion of Methane Using Genetic Algorithms
Plasma chemistry and plasma processing x, x () [10.1007/s11090-021-10159-6]  Download fulltext Files BibTeX | EndNote: XML, Text | RIS

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A sensitivity analysis of numerical predictions for beryllium erosion and migration in ITER
Nuclear materials and energy 26, 100904 - () [10.1016/j.nme.2021.100904] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Simulation of Impurity Transport and Deposition in the Closed Helical Divertor in the Large Helical Device
Plasma and fusion research 16(0), 2403004 () [10.1585/pfr.16.2403004] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Quantification of erosion pattern using picosecond-LIBS on a vertical divertor target element exposed in W7-X
Nuclear fusion 61(1), 016025 - () [10.1088/1741-4326/abc408] Embargoed OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

Sonstige Veröffentlichungen 2021

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Role of drifts, impurities and neutrals for credible predictions of radiation and power flux asymmetries in the DEMO scrape-off layer
28th IAEA Fusion Energy Conference (FEC 2020), virtuellvirtuell, virtuell, 10 May 2021 - 15 May 20212021-05-102021-05-15 1 - 8 () OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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CONTROL OF THE X-POINT RADIATOR IN FULLYDETACHED ASDEX UPGRADE H-MODE PLASMAS
28th IAEA Fusion Energy Conference (FEC 2020), virtuellvirtuell, virtuell, 10 May 2021 - 15 May 20212021-05-102021-05-15 1- 8 () OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Plasma-Surface Interaction in the Stellarator W7-X: Conclusion drawn from operation with Graphite Plasma-Facing Components
28th IAEA Fusion Energy Conference (FEC 2020), virtuellvirtuell, virtuell, 10 May 2021 - 15 May 20212021-05-102021-05-15 1-7 () OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Latest results of EUROfusion plasma-facing components research in the areas of power loading, material erosion and fuel retention
28th IAEA Fusion Energy Conference (FEC 2020), virtuellvirtuell, virtuell, 10 May 2021 - 15 May 20212021-05-102021-05-15 1 - 7 ()  Download fulltext Files BibTeX | EndNote: XML, Text | RIS

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High fluence steady-state and high cycle number ELM-like loading of ITER-like monoblocks in Magnum-PSI
28th IAEA Fusion Energy Conference (FEC 2020), virtuellvirtuell, virtuell, 10 May 2021 - 15 May 20212021-05-102021-05-15 1-5 () OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Predictive 3D modelling of erosion and deposition in ITER with ERO2.0: from beryllium main wall, tungsten divertor to full-tungsten device
18th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-18), virtuellvirtuell, virtuell, 17 May 2021 - 21 May 20212021-05-172021-05-21 1-4 ()  Download fulltext Files BibTeX | EndNote: XML, Text | RIS

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Gross and net erosion balance of plasma-facing components in full-W tokamaks
28th IAEA Fusion Energy Conference (FEC 2020), virtuellvirtuell, virtuell, 10 May 2021 - 15 May 20212021-05-102021-05-15 1-5 () OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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EXPERIMENTAL IMPURITY CONCENTRATIONS REQUIRED TO REACH DETACHMENT ON AUG AND JET
28th IAEA Fusion Energy Conference (FEC 2020), virtuellvirtuell, virtuell, 10 May 2021 - 15 May 20212021-05-102021-05-15 1-5 () OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Shattered Pellet Injection experiments at JET in support of the ITER Disruption Mitigation System design
28th IAEA Fusion Energy Conference (FEC 2020), virtuellvirtuell, virtuell, 10 May 2021 - 15 May 20212021-05-102021-05-15 1-7 () OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Scaling of deuterium retention in < 3 MeV proton damaged Beryllium, Eurofer, and W-5Re in the range of 0.0003 to 6 DPA
18th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-18), virtuellvirtuell, virtuell, 17 May 2021 - 21 May 20212021-05-172021-05-21 1-5 ()  Download fulltext Files BibTeX | EndNote: XML, Text | RIS

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Double pulse laser-induced breakdown spectroscopy for plasma facing component analysis
18th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-18), virtuellvirtuell, virtuell, 17 May 2021 - 21 May 20212021-05-172021-05-21 1-5 () OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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EXPERIMENTAL INDICATIONS OF HIGH-RECYCLING AND THE ROLE OF PLASMA PRESSURE AND POWER DISSIPATION IN THE DETACHMENT EVOLUTION AT W7-X
28th IAEA Fusion Energy Conference (FEC 2020), virtuellvirtuell, virtuell, 10 May 2021 - 15 May 20212021-05-102021-05-15 1-6 () OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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A sensitivity analysis of numerical predictions forberyllium erosion and migration in ITER
24th International Conference on Plasma Surface Interactions in Controlled Fusion Devices (PSI 2020), virtuellvirtuell, virtuell, 25 Jan 2021 - 29 Jan 20212021-01-252021-01-29 1-12 () OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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A sensitivity analysis of numerical predictions for beryllium erosion and migration in ITER
24th International Conference on Plasma Surface Interactions in Controlled Fusion Devices (PSI 2020), virtuellvirtuell, virtuell, 25 Jan 2021 - 29 Jan 20212021-01-252021-01-29 1-13 () OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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ERO2.0 - full 3D modelling of global material erosion, transport and deposition in fusion devices
28th IAEA Fusion Energy Conference (FEC 2020), virtuellvirtuell, virtuell, 10 May 2021 - 15 May 20212021-05-102021-05-15 1-6 ()  Download fulltext Files BibTeX | EndNote: XML, Text | RIS

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MULTI-MACHINE SOLPS-ITER COMPARISON OF IMPURITY SEEDED H-MODE RADIATIVE DIVERTOR REGIMES WITH METAL WALLS
28th IAEA Fusion Energy Conference (FEC 2020), virtuellvirtuell, virtuell, 10 May 2021 - 15 May 20212021-05-102021-05-15 1-7 ()  Download fulltext Files BibTeX | EndNote: XML, Text | RIS

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Impact of plasma-wall interaction and exhaust on the EU-DEMO design
24th International Conference on Plasma Surface Interactions in Controlled Fusion Devices (PSI 2020), virtuellvirtuell, virtuell, 25 Jan 2021 - 29 Jan 20212021-01-252021-01-29 () OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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LIBS FOR MONITORING OF TRITIUM AND IMPURITIES IN THE FIRST WALL OF FUSION DEVICES
28th IAEA Fusion Energy Conference (FEC 2020), virtuellvirtuell, virtuell, 10 May 2021 - 15 May 20212021-05-102021-05-15 1-7 () OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS