| Use of tungsten material for the ITER divertor T Hirai, S Panayotis, V Barabash, C Amzallag, F Escourbiac, A Durocher, ... Nuclear Materials and Energy 9, 616-622, 2016 | 350 | 2016 |
| Challenges for plasma-facing components in nuclear fusion J Linke, J Du, T Loewenhoff, G Pintsuk, B Spilker, I Steudel, M Wirtz Matter and Radiation at Extremes 4 (5), 2019 | 239 | 2019 |
| Performance of different tungsten grades under transient thermal loads J Linke, T Loewenhoff, V Massaut, G Pintsuk, G Ritz, M Rödig, A Schmidt, ... Nuclear Fusion 51 (7), 073017, 2011 | 201 | 2011 |
| Baseline high heat flux and plasma facing materials for fusion Y Ueda, K Schmid, M Balden, JW Coenen, T Loewenhoff, A Ito, ... Nuclear Fusion 57 (9), 092006, 2017 | 182 | 2017 |
| Plasma–wall interaction studies within the EUROfusion consortium: progress on plasma-facing components development and qualification S Brezinsek, JW Coenen, T Schwarz-Selinger, K Schmid, A Kirschner, ... Nuclear fusion 57 (11), 116041, 2017 | 138 | 2017 |
| Tungsten and CFC degradation under combined high cycle transient and steady state heat loads T Loewenhoff, J Linke, G Pintsuk, C Thomser Fusion Engineering and Design 87 (7-8), 1201-1205, 2012 | 113 | 2012 |
| Evolution of tungsten degradation under combined high cycle edge-localized mode and steady-state heat loads T Loewenhoff, A Bürger, J Linke, G Pintsuk, A Schmidt, L Singheiser, ... Physica Scripta 2011 (T145), 014057, 2011 | 99 | 2011 |
| Operating a full tungsten actively cooled tokamak: overview of WEST first phase of operation J Bucalossi, J Achard, O Agullo, T Alarcon, L Allegretti, H Ancher, G Antar, ... Nuclear Fusion 62 (4), 042007, 2022 | 92 | 2022 |
| Overview of progress in European medium sized tokamaks towards an integrated plasma-edge/wall solution a H Meyer, T Eich, M Beurskens, S Coda, A Hakola, P Martin, J Adamek, ... Nuclear Fusion 57 (10), 102014, 2017 | 84 | 2017 |
| Thermal shock tests to qualify different tungsten grades as plasma facing material M Wirtz, J Linke, T Loewenhoff, G Pintsuk, I Uytdenhouwen Physica scripta 2016 (T167), 014015, 2016 | 82 | 2016 |
| Real-time-capable prediction of temperature and density profiles in a tokamak using RAPTOR and a first-principle-based transport model F Felici, J Citrin, AA Teplukhina, J Redondo, C Bourdelle, F Imbeaux, ... Nuclear Fusion 58 (9), 096006, 2018 | 79 | 2018 |
| Material properties and their influence on the behaviour of tungsten as plasma facing material M Wirtz, I Uytdenhouwen, V Barabash, F Escourbiac, T Hirai, J Linke, ... Nuclear Fusion 57 (6), 066018, 2017 | 71 | 2017 |
| Impact of combined transient plasma/heat loads on tungsten performance below and above recrystallization temperature T Loewenhoff, S Bardin, H Greuner, J Linke, H Maier, TW Morgan, ... Nuclear fusion 55 (12), 123004, 2015 | 64 | 2015 |
| Self-castellation of tungsten monoblock under high heat flux loading and impact of material properties S Panayotis, T Hirai, V Barabash, A Durocher, F Escourbiac, J Linke, ... Nuclear Materials and Energy 12, 200-204, 2017 | 58 | 2017 |
| Transient heat load challenges for plasma-facing materials during long-term operation M Wirtz, J Linke, T Loewenhoff, G Pintsuk, I Uytdenhouwen Nuclear Materials and Energy 12, 148-155, 2017 | 51 | 2017 |
| ITER-W monoblocks under high pulse number transient heat loads at high temperature T Loewenhoff, J Linke, G Pintsuk, RA Pitts, B Riccardi Journal of Nuclear Materials 463, 202-205, 2015 | 46 | 2015 |
| Additive manufacturing of high density pure tungsten by electron beam melting D Dorow-Gerspach, A Kirchner, T Loewenhoff, G Pintsuk, T Weißgärber, ... Nuclear materials and energy 28, 101046, 2021 | 43 | 2021 |
| Emissivity measurement of tungsten plasma facing components of the WEST tokamak J Gaspar, C Pocheau, Y Corre, N Ehret, D Guilhem, M Houry, T Loarer, ... Fusion Engineering and Design 149, 111328, 2019 | 40 | 2019 |
| Calculation of cracking under pulsed heat loads in tungsten manufactured according to ITER specifications AS Arakcheev, DI Skovorodin, AV Burdakov, AA Shoshin, SV Polosatkin, ... Journal of Nuclear Materials 467, 165-171, 2015 | 39 | 2015 |
| Performance assessment of thick W/Cu graded interlayer for DEMO divertor target M Richou, F Gallay, B Böswirth, I Chu, G Dose, H Greuner, G Kermouche, ... Fusion engineering and design 157, 111610, 2020 | 38 | 2020 |
Dr. Marius WirtzForschungszentrum Jülich在 fz-juelich.de 的电子邮件经过验证
