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Guoliang Xu (ASIPP)18/05/2026, 09:30B. Material Erosion, Migration, Mixing, and Dust FormationOral
A SOLPS-DIVIMP-SDTRIM.SP integrative modeling framework has been established to simulate time-dependent material erosion, impurity transport, and boundary plasma transport for > 100s long-pulse discharges in EAST for the first time. The erosion and redeposition of plasma-facing materials (PFMs) during long-pulse discharges not only affect the boundary plasma conditions but also determine the...
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Fredric Granberg18/05/2026, 09:50B. Material Erosion, Migration, Mixing, and Dust FormationOral
The plasma facing materials of fusion reactors are subjected to harsh environments, and especially to possible synergetic effects of several different factors at once. To understand both the effects of single factors and their synergistic effects, we
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need to understand the phenomena at the atomistic level. Molecular dynamics (MD) simulations have been utilized to understand these phenomena,... -
Mamoru Shoji (National Institute for Fusion Science)18/05/2026, 11:10B. Material Erosion, Migration, Mixing, and Dust FormationOral
Time-resolved simulations of erosion on tungsten-coated divertor plates in the Large Helical Device (LHD) were performed using ERO2.0, a three-dimensional Monte Carlo code for plasmaโsurface interaction analysis [1]. The temporal evolution of the erosion areas during the experimental campaign was investigated using a new modeling approach that accounts for time-dependent changes in surface...
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Prof. David Donovan (University of Tennessee-Knoxville)18/05/2026, 11:30B. Material Erosion, Migration, Mixing, and Dust FormationOral
The transport of tungsten (W) impurities from W-coated plasma-facing components (PFCs) in the largely carbon (C) environment of the DIII-D tokamak was assessed leading to refinements of the existing modeling and theory framework that will be needed as the fusion community advances to high-Z PFC operations while maintaining a mixed-material environment in transition. Recent progress at DIII-D...
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Jin Guo (ASIPP)18/05/2026, 13:50H. Far SOL Transport and Plasma Wall Interaction in Main ChamberOral
The energy distribution of charge-exchange neutral (CXN) measured on EAST is interpreted by SOLPS-ITER modeling with the wide grid version, and the CXN-induced all erosion near the inner midplane and baffles is found to be significant especially under the enhanced SOL transport regime. Simulations for ITER predict that plasma and CXN fluxes onto the first wall are very sensitive to the...
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Henri Kumpulainen (FZJ)18/05/2026, 14:10E. Impurity Sources, Transport and ControlOral
The physical sputtering rate of tungsten (W) and its sensitivity to scrape-off-layer (SOL) fluctuations is characterised as the first application of time-dependent ERO2.0 [1] full-orbit Monte Carlo simulations in fluctuating turbulent plasma conditions. A time-dependent 3D description of global edge-SOL turbulence is obtained from validated GRILLIX [2] simulations. The studied plasma scenario...
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Dr Guido Ciraolo (IRFM CEA)18/05/2026, 14:30E. Impurity Sources, Transport and ControlOral
With the transition to full tungsten (W) plasma-facing components in ITER, the modeling of plasma wall interaction and the prediction of W erosion, transport and screening it has become a crucial issue for preparing ITER operation. In this context the development of improved modeling tools able to predict W behavior and its impact on plasma performances as well as the transport of seeded...
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Prof. Narguess Nemati (Department of Mechanical and Production Engineering, Aarhus University, Katrinebjergvej, Aarhus N, 8200, Denmark)19/05/2026, 09:10J. Plasma Exhaust and Plasma Material Interactions for Fusion ReactorsOral
Abnormal grain growth (AGG) has been reported in tungsten monoblock divertor targets after repetitive high-heat-flux (HHF) exposure, raising questions about the specific role of steep divertor thermal gradients in triggering this behavior. In this contribution, we use an experiment-informed coupled modeling framework to ask: are fusion-relevant transient thermal gradients, by themselves,...
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Florian Effenberg (PPPL)19/05/2026, 09:30A. Physics Processes at the Plasma Material InterfaceOral
A coordinated campaign of experiments in the DIII-D tokamak has advanced the qualification of plasma-facing materials (PFMs) through national laboratory and university efforts together with publicโprivate partnerships. Candidate materials included W alloys, additively manufactured (AM) W, K-doped W, neutron-irradiated W and ceramics, high-entropy and multi-principal-element alloys,...
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Dr Stephanie Pitts (Idaho National Laboratory)19/05/2026, 10:50J. Plasma Exhaust and Plasma Material Interactions for Fusion ReactorsOral
Reliable material performance is required for plasma-facing material (PFM) candidates. Previous research has shown that plasma and neutron radiation exposure induces microstructural changes in PFMs; changes in thermal and electrical conductivities and in material hardening and embrittlement were also observed after neutron irradiation. These material property changes will negatively impact the...
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Johann Riesch (MPPL)19/05/2026, 11:10J. Plasma Exhaust and Plasma Material Interactions for Fusion ReactorsOral
Tungsten heavy alloys (WHA) consisting of tungsten with small amounts (few weight %) of nickel (Ni) and iron (Fe) or copper (Cu) are ductile and tough materials, which could in some cases replace brittle bulk tungsten as a plasma-facing material. Therefore, such materials are considered for moderately loaded areas in current and future fusion reactors, e.g. the stellarator W7-X, the high-field...
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Prof. Daniel Andruczyk (University of Illinois Urbana-Champaign)19/05/2026, 11:30J. Plasma Exhaust and Plasma Material Interactions for Fusion ReactorsOral
The Hybrid Illinois Device for Research and Application (HIDRA) is located at the Center for Plasma Material Interactions (CPMI) at the University of Illinois Urbana-Champaign. It is a 5-period classical stellarator with an on-axis magnetic field B0 < 0.5 T. It is capable of true steady state operation with plasma discharge length up to, t < 10,000 s in duration with typical experimental...
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James Gunn (CEA)19/05/2026, 14:20F. Edge and Divertor Plasma PhysicsOral
Ion temperature measurements on the lower divertor of the WEST tokamak from attached plasmas to detached and X-point radiator regimes
J. P. Gunn,1 P. Ivanova,2 M. Dimitrova,2,3 J. Kovaฤic4
1 CEA, IRFM, F-13108 Saint-Paul-Lez-Durance, France.
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2 Emil Djakov Institute of Electronics, Bulgarian Academy of Sciences, 72, Tsarigradsko Chaussee Blvd., 1784 Sofia, Bulgaria.
3 Institute of... -
Ou Pan (Max Planck Institute for Plasma Physics)19/05/2026, 14:40G. Power Exhaust, Plasma Detachment and Heat Load ControlOral
Future fusion reactors require integrated operating scenarios that simultaneously address divertor power exhaust, tungsten impurity control, and good core confinement. In recent JET campaigns, dedicated โJET-ITER baselineโ experiments with neon impurity seeding were conducted in D and D-T plasmas [1], developed at high input power (30-35 MW), high plasma current (2.5-3.2 MA), high density...
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Tobias Tork (MPPL)20/05/2026, 09:10F. Edge and Divertor Plasma PhysicsOral
Particle drifts play a crucial role in the understanding of the edge physics of current and future fusion devices. While tokamak simulations routinely include drift effects, they have been largely neglected in stellarator simulations until now. The low field line pitch in a stellarator amplifies the relative importance of drifts compared to the parallel transport. Experiments in Wendelstein...
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Andreas Dinklage (MPPL)20/05/2026, 10:00C. Plasma Fueling, Particle Exhaust and Control, Tritium RetentionOral
Stellarators intrinsically avoid pulse-length limitations of the magnetic confinement, since the rotational transform is generated by external coils rather than by a plasma current. We report on the development of discharge scenarios that enable long-term stabilization of high-performance plasmas in the optimized stellarator W7-X. For the first time, dimensionless parameters of reactor...
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Filippo Scotti, Huiqian Wang (General Atomics)20/05/2026, 10:50G. Power Exhaust, Plasma Detachment and Heat Load ControlOral
Recent DIII-D experiments have demonstrated the compatibility of divertor detachment with a high normalized beta core, a significant step towards solving the core-edge integration issue for steady-state fusion. The high-confinement, high-beta operation leveraging both high beta hybrid and high poloidal-beta approaches greatly improves core performance under dissipative divertor operation....
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Dr David Tskhakaya (Institute of Plasma Physics of the CAS, Za Slovankou 1782/3, 182 00 Prague 8, Czech Republic)20/05/2026, 11:40F. Edge and Divertor Plasma PhysicsOral
Plasma detachment is a common divertor regime in tokamaks and stellarators. Plasma and power exhaust properties in this regime are described by classical magnetized plasma models including the plasma sheath [1]. However, the classical sheath model can fail with increasing plasma density and collisionality when plasma ions can be demagnetized and no longer follow magnetic field lines....
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Richard Ducker (EPFL)20/05/2026, 12:00F. Edge and Divertor Plasma PhysicsOral
A new Tangential Divertor Spectrometer System (TDSS) on the TCV tokamak provides, for the first time, simultaneous measurements of ion temperature and parallel flow poloidal and radial profiles in the divertor Scrape-Off Layer (SOL). High spectral resolution enables the identification of the emission region through Zeeman splitting, allowing for the reconstruction of radial profiles using the...
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Dr Miroslaw Zlobinski (Forschungszentrum Jรผlich GmbH)21/05/2026, 08:40C. Plasma Fueling, Particle Exhaust and Control, Tritium RetentionOral
In the final divertor setup of JET, the divertor bottom consisted of 4 toroidal rings of thin, separated bulk-W lamellae called โtile 5โ or load-bearing septum replacement plates (LBSRP). [1]
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Three of the lamellae studied here had been exposed during JET plasma operation only during the ITER-like wall campaign 1 (ILW1) and another three lamellae in addition during the ITER-like wall campaign... -
Anลพe Zaloลพnik (UCSD)21/05/2026, 09:30J. Plasma Exhaust and Plasma Material Interactions for Fusion ReactorsOral
Increased hydrogen isotope retention in materials damaged by energetic neutrons has been a major concern for the operation of fusion reactors, as it leads to the loss of precious fusion fuel. Laboratory studies on the effect of such damage on deuterium (D) retention in tungsten (W) rely primarily on self-ion damaging of the material as a surrogate for neutrons. Most such studies were performed...
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Dr Antonello Zito (Max-Planck-Institut fรผr Plasmaphysik, Garching, Germany)21/05/2026, 10:50F. Edge and Divertor Plasma PhysicsOral
Fuel and impurity density control is essential to ensure reliable tokamak operations. This requires a deep understanding of the physical mechanisms determining the transport of particles in the plasma edge and the pumping of these in form of neutrals.
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Divertor compression is the main physics-based figure of merit characterizing particle exhaust efficiency. High-fidelity transport models... -
Elena Tonello (SPC - EPFL)21/05/2026, 11:10F. Edge and Divertor Plasma PhysicsOral
This work presents an extensive SOLPS-ITER validation effort on the TCV tokamak, built around a global, multi-diagnostic comparison between simulations and systematic experimental databases. Accurate modelling of the scrape-off layer (SOL) and divertor plasma is essential for predicting wall erosion, impurity transport, and heat dissipation in present and future tokamaks. Quantitatively...
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Bart Lomanowski (Oak Ridge National Laboratory)21/05/2026, 11:30F. Edge and Divertor Plasma PhysicsOral
Progress in mapping the tokamak operational space to the separatrix plasma parameters via the separatrix operating space framework (SepOS [1]) has enabled cross-machine comparisons of small/no-ELM regime access (e.g., QCE [2] or EDA H-mode [3]). In this work we extrapolate the SepOS projections to SPARC and ITER, and, crucially, introduce detachment access criteria, thus formulating the...
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Matteo Moscheni (Gauss Fusion GmbH, Parkring 29, 85748 Garching bei Mรผnchen, Germany)21/05/2026, 11:50C. Plasma Fueling, Particle Exhaust and Control, Tritium RetentionOral
The transition from a hot, clean core to a dissipative, engineering-compatible edge renders separatrix density $n_{\text{sep}}$ and impurity concentration $c_{\text{sep}}$ central to confinement, pedestal stability and detachment control. Predicting them reliablyโand quantifying their link to the true experimental actuators of fueling and seeding puffing ratesโremains a key objective for...
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Yaowei Yu (Institute of Plasma Physics, Chinese Academy of Sciences)21/05/2026, 14:10F. Edge and Divertor Plasma PhysicsOral
Particle recycling and wall conditions play a crucial role in plasma confinement and long-pulse operation in tokamaks, yet their quantitative impact has not been clearly established. In EAST superconducting tokamak with full metal wall, a systematic statistical analysis was performed to assess the dependence of plasma stored energy on density, heating power, wall conditions, and...
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Garance Durr-Legoupil-Nicoud (EPFL)22/05/2026, 08:40G. Power Exhaust, Plasma Detachment and Heat Load ControlOral
On TCV and DIII-D, negative-triangularity (NT) plasmas have demonstrated good, reactor-relevant energy confinement while remaining in L-mode, thereby avoiding major H-mode power-exhaust issues such as ELMs and the LโH power threshold. On TCV, Ohmic studies found that NT plasmas were harder to detach than similar positive-triangularity (PT) plasmas [1], ascribed, in part, to a lower scrape-off...
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Diego Oliveira (CEA - IRFM)22/05/2026, 13:50F. Edge and Divertor Plasma PhysicsOral
Fusion reactors will operate with a strong scrape-off layer (SOL)/edge plasma-neutral interactions to benefit from the energy and momentum losses due to atomic reactions to protect the divertor walls, the so-called (semi) detached plasma. While access and basic properties of such regimes are well known, a complete and detailed understanding of the tokamak boundary of detached plasmas is...
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Thomas Body (Commonwealth Fusion Systems)22/05/2026, 14:10G. Power Exhaust, Plasma Detachment and Heat Load ControlOral
To manage erosion and protect against heat fluxes, tokamak power plants will need to be operated with detached divertors. To design future tokamaks around core-edge-integrated operating scenarios, we need fast, accurate detachment models. We developed a model to calculate the impurity concentration needed to detach the first $\lambda_q$ of the outer divertor. This model is based on the 0D...
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Renato Perillo (UCSD)22/05/2026, 15:00J. Plasma Exhaust and Plasma Material Interactions for Fusion ReactorsOral
Experimental analysis and simulations with the BOUT++ code[1] show that small edge-localized modes (ELMs) in reactor-relevant high-density regimes originate in a region close to the separatrix and only marginally perturb the pedestal structure. The measured divertor peak parallel energy flux for a database of small ELMs in DIII-D and ASDEX Upgrade can be reproduced, within 40% accuracy on...
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