Florian Effenberg
Staff Research Physicist
Staff Research Physicist
Florian Effenberg is a Staff Research Physicist at Princeton Plasma Physics Laboratory (PPPL) and Principal Investigator of a DOE Fusion Energy Sciences (FES)–funded multi-institutional program on predictive wall conditioning and plasma–material interactions in magnetic confinement fusion devices. He leads a multi-institutional research program (2025–2030) on predictive wall conditioning and surface evolution in metallic-wall tokamaks, addressing critical science and technology gaps in controlling plasma–material interactions for ITER and next-step fusion devices. He also serves as Deputy U.S. Tokamak Research Coordinator for plasma–material interactions (PMI) within the DOE FES Tokamak Research program, coordinating PMI research and validation efforts across multiple tokamak facilities, including DIII-D and KSTAR. He leads the International Tokamak Physics Activity (ITPA) Divertor and Scrape-Off Layer (DSOL) task on in-situ boron injection for impurity control in ITER-relevant scenarios and has led plasma-facing material and wall conditioning research at DIII-D, including serving as Deputy Lead of the Wall Change Preparation Task Force.
His research integrates experiments, modeling, and surface and boundary diagnostics to develop and validate predictive, metrics-driven models for impurity control and plasma-facing component (PFC) performance, including impurity control in tungsten environments, with emphasis on real-time low-Z material injection and core–edge integrated power exhaust in reactor-relevant conditions. This work supports predictive control of plasma-facing component behavior for ITER and future fusion pilot plants.
Effenberg received his Ph.D. in Nuclear Engineering and Engineering Physics from the University of Wisconsin–Madison, where he conducted research on three-dimensional edge plasma transport and radiative divertor operation in the Wendelstein 7-X stellarator. He led impurity seeding experiments and performed modeling using the EMC3-EIRENE edge transport code, for which he received the James D. Callen Fellowship for Excellence in Plasma Theory.
Following his Ph.D., he continued research on plasma–material interactions and power exhaust in stellarator experiments before joining PPPL in 2019. His work focuses on impurity transport modeling, real-time surface conditioning with low-Z materials, and integrated plasma–material interaction physics for ITER and future fusion pilot plants.
Contact:
Princeton Plasma Physics Laboratory
Tokamak Experimental Sciences Department
100 Stellarator Rd
Princeton, NJ 08540
USA
On research assignment at:
3550 General Atomics Ct
San Diego, CA 92121
USA
Publications:
Selected papers
F. Effenberg et al, 'Integrated modeling of boron powder injection for real-time plasma-facing component conditioning', Nuclear Materials and Energy 42, 101832, 2025, https://doi.org/10.1016/j.nme.2024.101832; arXiv:2407.00821v3, Accepted manuscript
F. Effenberg et al, 'In-situ coating of silicon-rich films on tokamak plasma-facing components with real-time Si material injection', Nucl. Fusion 63 106004, 2023, https://doi.org/10.1088/1741-4326/acee98; arXiv:2304.03923, Accepted manuscript
F. Effenberg et al, 'Mitigation of plasma-wall interactions with low-Z powders in DIII-D high confinement plasmas', Nuclear Fusion 62 106015, 2022, https://doi.org/10.1088/1741-4326/ac899d; arXiv:2203.15204, Accepted manuscript
F. Effenberg et al, '3D modeling of boron transport in DIII-D L-mode wall conditioning experiments', Nuclear Materials and Energy 26, 100900, 2021, https://doi.org/10.1016/j.nme.2021.100900 , Published manuscript
F. Effenberg et al, 'First demonstration of radiative power exhaust with impurity seeding in the island divertor at Wendelstein 7-X', Nuclear Fusion 59 (10), 106020, 2019, https://doi.org/10.1088/1741-4326/ab32c4 , Accepted manuscript
F. Effenberg et al 'Investigation of 3D effects on heat fluxes in performance-optimized island divertor configurations at Wendelstein 7-X', Nuclear Materials and Energy 18, 262-267, 2019, https://doi.org/10.1016/j.nme.2019.01.006, Published manuscript
F. Effenberg et al, 'Numerical investigation of plasma edge transport and limiter heat fluxes in Wendelstein 7-X startup plasmas with EMC3-EIRENE', Nucl. Fusion 57 036021, 2017, https://doi.org/10.1088/1741-4326/aa4f83, Accepted manuscript
J. Coburn, F. Effenberg et al, 'Overview of advanced plasma-facing materials testing for Fusion Pilot Plants at DIII-D', Nuclear Materials and Energy 46, 102064, 2026, https://doi.org/10.1016/j.nme.2026.102064
M. Morbey, F. Effenberg, et al, 'Deuterium retention in pre-lithiated samples and Li–D co-deposits in the DIII-D tokamak', Nuclear Materials and Energy 43, 101915, 2025, https://doi.org/10.1016/j.nme.2025.101915; arXiv:2502.18061
E.M. Hollmann, A. Bortolon, F. Effenberg et al, ' Dynamic measurement of impurity ion transport in runaway electron plateaus in DIII-D', Physics of Plasmas 29, 022503, 2022, https://doi.org/10.1063/5.0080385
K. Schmid, F. Effenberg et al, 'Integrated modeling: Coupling of surface evolution and plasma-impurity transport', Nuclear Materials and Energy, Volume 25, 100821, 2020, https://doi.org/10.1016/j.nme.2020.100821
H. Niemann, M.W. Jakubowski, F. Effenberg et al, 'Features of near and far scrape-off layer heat fluxes on the Wendelstein 7-X inboard limiters', Nucl. Fusion 60 016014, 2020, https://doi.org/10.1088/1741-4326/ab472c
V. Perseo, F. Effenberg et al, 'Direct measurements of counter-streaming flows in a low-shear stellarator magnetic island topology', Nucl. Fusion 59 124003, 2019, https://doi.org/10.1088/1741-4326/ab4320
T. Barbui, F. Effenberg et al, 'Radiative edge cooling experiments in Wendelstein 7-X start-up limiter campaign', Nucl. Fusion 59 076008, 2019, https://doi.org/10.1088/1741-4326/ab18c5, Accepted manuscript
L. Stephey, A. Bader, F. Effenberg et al, 'Impact of magnetic islands in the plasma edge on particle fueling and exhaust in the HSX and W7-X stellarators’, Physics of Plasmas 25, 062501 2018, https://doi.org/10.1063/1.5026324, Accepted manuscript
H. Frerichs, F. Effenberg et al, 'Reconstruction of recycling flux from synthetic camera images, evaluated for the Wendelstein 7-X startup limiter', Nucl. Fusion 57 126022, 2017, https://doi.org/10.1088/1741-4326/aa8515, Accepted manuscript
G.A. Wurden, C. Biedermann, F. Effenberg et al, 'Limiter observations during W7-X first plasmas', Nucl. Fusion 57 056036, 2017, https://doi.org/10.1088/1741-4326/aa6609
Selected conference contributions
F. Effenberg et al, 'Reducing tungsten plasma-material interactions with boron and boron nitride powders in the DIII-D V-shaped divertor', poster, video, 65th Annual Meeting of the APS Division of Plasma Physics Oct 30-Nov 3, 2023, Denver, CO, USA
F. Effenberg et al, 'Reducing plasma-material interactions in the DIII-D low-Z and high-Z divertors with impurity powders', poster, 29th IAEA Fusion Energy Conference (FEC 2023) 16–21 October 2023, London, United Kingdom
F. Effenberg et al, 'In situ growth and replenishment of PFC coatings with real-time material injection for enhanced steady-state plasma operation', contributed talk, The IEEE Symposium on Fusion Engineering, (SOFE 2023), July 9–13, 2023; UK Atomic Energy Authority; Oxford, UK
F. Effenberg et al, 'EMC3-EIRENE modeling of toroidally-localized material injections and its effect on plasma-material interactions', contributed talk, 19th International Conference on Plasma-Facing Materials and Components for Fusion Applications, (PFMC-19), May 22–26, 2023; Bonn, Germany
F. Effenberg et al, 'In-situ growth of silicon-rich layers with Si granule injection in DIII-D H-mode plasmas', poster, 25nd International Conference on Plasma Surface Interactions 2022, (PSI-25), June 13–17, 2022; Jeju, Korea
F. Effenberg et al, 'Mitigation of plasma-material interactions with low-Z powders in DIII-D H-mode discharges', invited talk, video, 63rd Annual Meeting of the APS Division of Plasma Physics, November 8–12, 2021; Pittsburgh, PA, USA
F. Effenberg et al, '3D modeling of boron transport in DIII-D L-mode real-time wall conditioning experiments', poster, video, 24th International Conference on Plasma Surface Interaction in Fusion Devices (PSI-24), Jeju, Korea, May 31st - June 5, 2020
F. Effenberg et al, 'Development of impurity seeding for divertor power flux handling in Wendelstein 7-X long pulse scenarios', poster, The 19th International Conference on Fusion Reactor Materials (ICFRM-19), Oct 27 – Nov 1, 2019, La Jolla, California, USA
F. Effenberg et al, 'Radiative Power Exhaust in the Island Divertor and Access to Controlled Detachment with Impurity Seeding’, contributed talk, 22nd International Stellarator and Heliotron Workshop 2019 (ISHW 2019), Madison, WI, USA
F. Effenberg et al, ‘Power Exhaust Control by Impurity Seeding in the Island Divertor at Wendelstein 7-X', contributed talk, 27th IAEA Fusion Energy Conference (FEC 2018), 22-27 Oct 2018, Ahmedabad, India
F. Effenberg et al, 'Exploration of Radiative Edge Cooling in the Island Divertor at Wendelstein 7-X', contributed talk, 23rd International Conference on Plasma Surface Interactions in Controlled Fusion Devices (PSI 23), Princeton, NJ, 17-22 June 2018
F. Effenberg et al, 'Analysis of the heat flux characteristics in the helical scrape-off layer of Wendelstein 7-X start up scenarios by 3-D modeling', contributed talk, 58th Annual Meeting of the APS Division of Plasma Physics, Oct 31 - Nov 4, 2016, San Jose, CA, USA
More to be found: google scholar or NCBI