Name: 27th PSI
Start: 2026-05-17T10:00:00+02:00
End: 2026-05-22T17:00:00+02:00
Location: marinaforum REGENSBURG

27th PSI

from Sunday, 17 May 2026 (10:00) to Friday, 22 May 2026 (17:00)

Monday, 11 May 2026
Tuesday, 12 May 2026
Wednesday, 13 May 2026
Thursday, 14 May 2026
Friday, 15 May 2026
Saturday, 16 May 2026
Sunday, 17 May 2026
13:00 T1 S. Brezinsek: An Introduction to Plasma Wall Interactions - Sebastijan Brezinsek (Forschungszentrum Jülich GmbH, Institute of Fusion Energy and Nuclear Waste Management – Plasma Physics, 52425 Jülich, Germany. Faculty of Mathematics and Natural Sciences, Heinrich Heine University Düsseldorf, 40225 Düsseldorf, Germany.)
T1 S. Brezinsek: An Introduction to Plasma Wall Interactions
- Sebastijan Brezinsek (Forschungszentrum Jülich GmbH, Institute of Fusion Energy and Nuclear Waste Management – Plasma Physics, 52425 Jülich, Germany. Faculty of Mathematics and Natural Sciences, Heinrich Heine University Düsseldorf, 40225 Düsseldorf, Germany.)
13:00 - 14:00
14:00 T2 P. Manz: Introduction to Scrape Off Layer Turbulent Transport - Peter Manz (University Greifswald)
T2 P. Manz: Introduction to Scrape Off Layer Turbulent Transport
- Peter Manz (University Greifswald)
14:00 - 15:00
We begin with an introduction to instabilities in the near and far SOL and in the divertor region. Special attention is paid to plasma blobs or filaments. We then discuss saturation mechanisms. The special role of turbulence spreading is highlighted. Possibilities for reduced modelling are outlined.
15:00 Coffee Break
Coffee Break
15:00 - 15:20
15:20 T3 M. Rubel: Dust in Fusion Devices: 40 years of Research - Marek Rubel (Uppsala University, Sweden)
T3 M. Rubel: Dust in Fusion Devices: 40 years of Research
- Marek Rubel (Uppsala University, Sweden)
15:20 - 16:20
This contribution is based on over 40 years of dust research in several devices with consecutive modifications of plasma-facing materials (PFM): • JET from full metal wall in 1983-1984, via JET-C with different fuelling schemes (including full D-T in 1997) and three consecutive divertor models, to JET-ILW with Be and W wall components; • TEXTOR from full metal wall (1983-1984) to the boronised (also siliconized) carbon wall and bulk W test limiters; • EXTRAP-T2 reversed field pinch with graphite PFM. Holistic approach to dust studies in fusion devices comprises a broad range of plasma diagnostics (spectroscopy, imaging tools, magnetic sensors), tracer techniques for material migration, development and selection of collection and retrieval methods for secure material transfer to analytical laboratories where over 35 techniques for ex-situ material characterisation were used. A crucial element of the programme was on fuel retention analysis from total amounts of H, D, T to depth profiling, elemental micro-mapping, determination of specific tritium activity and fuel (D, T) quantification in individual dust grains, e.g. distinction of retention between C and metals in mixed samples of dust. Such integrated efforts have allowed for the determination/ identification of several generation mechanisms including not only disintegration of co-deposits, arcing, brittle destruction and metal splashing but also plasma-chemical effects and metal flaking. In addition, dust-related safety aspects have been experimentally addressed, e.g. particle mobility during in-vessel operations with remote handling, the impact of hot water and/or water vapour on dust generation from affected wall materials, and dust accumulation in filters of the vessel ventilation system Particular emphasis is given to: (i) boron species, its chemical form, role of boronisation as a marker in the growth of co-deposits; (ii) metal-based or metal-containing dust W, steel, Be in the form of splashes and droplets; (iii) metal oxides, WO$_2$, BeO, whose in-situ formation has been proven. The latter process may lead to quite severe material erosion and transport. The investigation of W presence in dust was often concentrated on searching for loose droplets. No solid evidence for such objects has been obtained either in JET-ILW or in TEXTOR. Very detailed microscopy data clearly indicate that splitting and then flaking of thin metal layers (<0.5 micrometre) occurs in overheated surfaces of bulk W components, e.g. Langmuir probes. This pathway of material loss should not be neglected in the estimates of global erosion.
16:20 T4 T. Looby: Tutorial on plasma power exhaust physics modeling with HEAT - Tom Looby (Commonwealth Fusion Systems)
T4 T. Looby: Tutorial on plasma power exhaust physics modeling with HEAT
- Tom Looby (Commonwealth Fusion Systems)
16:20 - 17:20
Tokamaks such as SPARC or ITER will operate at high fusion performance to achieve energy gains on the order of Q~10. These high performance burning plasmas will generate extreme plasma power exhaust due to the narrowing of the heat flux channel as plasma current increases. In SPARC, for example, the steady state parallel heat fluxes are projected to reach 10 GW/m$^2$. Operating a tokamak safely under such loads is a key challenge for burning plasma machines and fusion power plants. This tutorial introduces the physics of tokamak power exhaust and a suite of codes used to predict the thermal loads onto PFCs. The HEAT code bridges the gap between plasma power exhaust physics and engineering CAD geometry. HEAT integrates a variety of plasma physics modules including the optical approximation, gyro orbit tracing, ELM filament tracing, runaway electron transport, photon transport, and 3D field heat loads using M3DC1. These physics solvers are coupled to FEM/FVM modules for calculating the PFC temperature, thermal stress, and tungsten recrystallization kinetics. This tutorial session will guide attendees through descriptions of the physics behind each of the HEAT modules, and practical examples of validation and verification will be provided from across the tokamak fleet. An analysis of gyro orbit effects will be provided for NSTX-U. Differentiating between SOL transport channels will be demonstrated with results from ASDEX Upgrade. The effects of 3D fields on the heat flux footprint will be discussed for DIII-D. And leveraging the knowledge of power exhaust physics to optimize PFCs for power handling will be shown for SPARC.

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