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27th PSI

17–22 May 2026
marinaforum REGENSBURG
Europe/Berlin timezone

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Session

Review Talk

Review
18 May 2026, 08:50
marinaforum REGENSBURG

marinaforum REGENSBURG

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R1

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  1. 14. R1 Modeling first wall erosion and impurity migration: from layer formation to W-core ingress
    Klaus Schmid (MPPL)
    18/05/2026, 08:50
    B. Material Erosion, Migration, Mixing, and Dust Formation
    Review

    Erosion of the first wall and transport of impurities critically affect the operation of magnetic confinement fusion devices. Erosion limits component lifetimes, while high-Z impurity penetration into the core increases radiation and can degrade confinement. For low-Z materials, repeated transport and re-deposition lead to long-range migration and formation of co-deposited layers that can...

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  2. 19. R2 Cracking and local ageing of tungsten plasma facing components – does it matters?
    ALAN DURIF (CEA, IRFM, CEA, F-13108 Saint Paul lez Durance, France)
    19/05/2026, 08:00
    J. Plasma Exhaust and Plasma Material Interactions for Fusion Reactors
    Review

    Tungsten (W) is widely used as a plasma-facing material in fusion devices due to its high melting point, low sputtering yield, and excellent thermal conductivity [1]. However, due its mechanical behaviour it is prone to crack under harsh experimental fusion environments: high heat fluxes (cycling steady state loading, ELMs & disruption) [2], light impurities bombardment (H, D, He) [3]....

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  3. 16. R3 Stellarator island divertor physics in Wendelstein 7-X: Current understanding and remaining challenges towards a reactor exhaust concept
    Felix Reimold (MPPL)
    20/05/2026, 08:00
    F. Edge and Divertor Plasma Physics
    Review

    Wendelstein 7-X (W7-X) operation successfully demonstrated power and particle exhaust with the island divertor. It is compatible with high performance operation using steady-state pellet fueling and homogenous detachment up to the current maximum heating power of 8 MW. However, the current open divertor geometry suffers from an unfavorable, approximately linear scaling of divertor density and...

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  4. 30. R4 Progress in understanding and modelling of fuel retention in view of future fusion devices with metallic walls
    Dmitry Matveev (FZJ)
    21/05/2026, 08:00
    C. Plasma Fueling, Particle Exhaust and Control, Tritium Retention
    Review

    For future burning-plasma fusion devices that will operate with a D-T fuel mix, the scarcity and radioactivity of tritium represent critical constraints on reactor safety and availability. Therefore, it has long been recognized that tritium retention and accumulation in Plasma-Facing Components (PFCs), along with its permeation into structural materials and cooling loops, require continuous...

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  5. 25. R5 Alternative divertor research – from physics studies to reactor implementation
    Christian Theiler (EPFL-SPC)
    22/05/2026, 08:00
    G. Power Exhaust, Plasma Detachment and Heat Load Control
    Review

    Handling plasma exhaust without compromising core performance remains one of the central challenges for fusion energy. Research on alternative divertor configurations (ADCs) has progressed rapidly in recent years, moving beyond exploratory studies [1,2] toward demonstrations of substantial benefits [3–5]. Reported advantages include order-of-magnitude reductions in target heat flux, extended...

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