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Jonathan Van Blarcum (ITER Organization (IO))19/05/2026, 16:20H. Far SOL Transport and Plasma Wall Interaction in Main ChamberPoster
EMC3-EIRENE scrape-off layer (SOL) simulations, with a domain extended to the first wall, are completed for the two scenarios which constitute the main targets of the Start of Research Operations (SRO) campaign in the ITER 2024 re-baseline: $B_T=5.3$ T, $I_P=15$ MA hydrogen L-modes and $B_T=2.65$ T, $I_P=7.5$ MA deuterium H-modes. These simulations also form part of a coordinated activity with...
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Luca Scotti (University of Milano-Bicocca)19/05/2026, 16:20H. Far SOL Transport and Plasma Wall Interaction in Main ChamberPoster
In future fusion reactors, the transient heat loads associated with large edge-localised modes (ELMs) are not tolerable, motivating strong interest in regimes with small or suppressed ELM activity. Among these, the Quasi-Continuous Exhaust (QCE) regime has emerged as particularly promising. It is characterised by the absence of large ELMs with a small confinement degradation. The QCE regime is...
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Dr Ayoub BENMOUMEN (Physics of the Interactions of Ions and Molecules (PIIM))19/05/2026, 16:20H. Far SOL Transport and Plasma Wall Interaction in Main ChamberPoster
In magnetic confinement nuclear fusion reactors, the tungsten (W) divertor (the main plasma-facing component) is exposed to extreme fluxes of helium (He) and hydrogen isotopes as well as high thermal loads. Despite tungsten’s strong thermo-mechanical properties (e.g. high melting point and high erosion resistance), the low solubility of He in W leads to the formation of near-surface He...
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Zeke Unterberg (Oak Ridge National Lab)19/05/2026, 16:20H. Far SOL Transport and Plasma Wall Interaction in Main ChamberPoster
Magnetic-confinement fusion energy (MFE) devices, including Pilot Plants and DEMOs, need to breed tritium if the D-T fuel cycle is used. Breeding blankets pose a new challenge for main wall plasma-facing component (PFC) design not faced until now since they must have thin (~mm’s) armoring to achieve a Tritium Breeding Ratio (TBR) > 1 [1]. By contrast, the ITER first wall thickness is ~10 cm...
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Audun Theodorsen (UiT - the Arctic University of Norway)19/05/2026, 16:20H. Far SOL Transport and Plasma Wall Interaction in Main ChamberPoster
The well-known two-point model [1, 2, 3] is a simple way to connect midplane and target conditions in the SOL. To further connect parallel and perpendicular SOL transport, average radial diffusive and advective transport of particles and heat is often assumed. However, the radial transport in the SOL is turbulent, consisting of plasma filaments of excess particles and heat driven by...
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Quan Shi (the University of Tokyo)19/05/2026, 16:20A. Physics Processes at the Plasma Material InterfacePoster
In future tokamak reactors, tungsten (W) is expected to serve as the main plasma-facing material. When subjected to helium (He) plasma—a byproduct of fusion reactions—and heated above 900 K, W surfaces can develop nanofiber-like structures known as "fuzz," which significantly degrade thermal conductivity [1]. This phenomenon has been linked to the dynamics of helium bubble formation and...
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SOOHYUN SON (KFE)19/05/2026, 16:20A. Physics Processes at the Plasma Material InterfacePoster
One of the most deleterious impurities is oxygen, which originates from the inevitable oxidation process in the material inside the tokamak. Boron (B) is an effective oxygen getter by easily forming chemical compounds such as boron oxide. Boronization is a commonly used method of wall conditioning that has been employed in various devices[1-3].
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In KSTAR, boronization was performed using... -
Dr Vadym Makhlai (National Science Center Kharkiv Institute of Physics and Technology, Kharkiv, Ukraine)19/05/2026, 16:20A. Physics Processes at the Plasma Material InterfacePoster
The synergistic effects of tungsten exposure to combined hydrogen and helium particle fluxes need to be extensively studied for the realization of a fusion reactor project. IGP tungsten (PLANSEE) with transversal grain 12125 mm3 was sequentially irradiated with a helium (He) ion beam and hydrogen plasma generated by QSPA at a surface temperature close to room temperature (RT). The ion energy...
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Hozane Blanche NGONGANG ELOKO (Aix Marseille Univ, CNRS, CINAM, Marseille, France)19/05/2026, 16:20A. Physics Processes at the Plasma Material InterfacePoster
In the context of nuclear fusion, the inner walls of the reactor are exposed to extremely high ion fluxes, particularly at the divertor, which collects most of the particles escaping from the plasma. Tungsten (W) is used for this component because of its high melting point, erosion resistance, low hydrogen retention and good thermal conductivity[1]. However, helium implantation induces the...
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John Caughman (Oak Ridge National Laboratory)19/05/2026, 16:20A. Physics Processes at the Plasma Material InterfacePoster
The presence of the radio frequency (RF) sheath can cause enhanced sputtering of plasma facing materials. Compared to a DC sheath with the same average potential, an RF sheath causes a broadening of the ion energy distribution function (IEDF) and results in enhanced light ion sputtering, especially for average RF sheath potentials close to the material sputtering threshold. The effect of RF...
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Jake Nichols (ORNL)19/05/2026, 16:20A. Physics Processes at the Plasma Material InterfacePoster
We present three-dimensional EMC3-EIRENE modeling of an MPEX-like linear plasma configuration, showing that access to a high-recycling regime can be maintained even at significantly oblique target angles via utilization of near-target neutral baffles. MPEX (Materials Plasma Exposure eXperiment) plans to expose candidate material targets to extreme plasma fluences in tokamak divertor-relevant...
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Athanasios Bamidis (Uppsala University)19/05/2026, 16:20A. Physics Processes at the Plasma Material InterfacePoster
In a future fusion reactor, energetic ions and neutrals escaping from the plasma will interact with plasma facing materials (PFM) on the first wall of the reactor. The impact of these particles will lead to modifications of the PFM, which in turn affects the performance, durability and safety of the reactor. Reliable modelling is therefore necessary to accurately predict these interaction and...
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Lorenzo Boccaccia (KTH Royal Institute of Technology)19/05/2026, 16:20A. Physics Processes at the Plasma Material InterfacePoster
The recent ITER re-baseline to an all-tungsten (W) reactor necessitates frequent boronizations, that will also lead to the production of intrinsic boron (B) dust whose transport and survivability should be well understood. Furthermore, it has been experimentally demonstrated that B powder injection can be utilized for real-time wall conditioning, pedestal control and turbulence suppression...
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Seiki Saito (Yamagata University)19/05/2026, 16:20A. Physics Processes at the Plasma Material InterfacePoster
Understanding the mechanisms of hydrogen recycling is a key factor in accurately predicting and managing plasma behavior in nuclear fusion reactors. In the present study, we develop a machine learning (ML) model capable of predicting the translational energy distributions and rovibrational states of hydrogen atoms and molecules emitted from tungsten plasma-facing components. These predictions...
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Tommaso Rizzi (KTH - Royal Institute of Technology)19/05/2026, 16:20A. Physics Processes at the Plasma Material InterfacePoster
Dust in D-T fusion reactors will be radioactive due to interactions with 14MeV neutrons and retention of tritium, which undergoes β-decay into helium with a 12.32yrs half-life. Tritium radioactive decay releases 18.6keV partitioned between an electron and anti-neutrino. The mean electron kinetic energy of 5.7keV suffices to traverse 200nm of W, implying that tritiated W dust constantly emits...
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Tatyana Sizyuk (ANL, USA)19/05/2026, 16:20A. Physics Processes at the Plasma Material InterfacePoster
Detailed 3D models of processes in materials subsurface and in plasma above the surface were recently developed and integrated into a single package, for the first time. This avoids uncertainties in predicting materials performance in fusion devices with complex geometries, magnetic, and electric fields. The upgraded ITMC-DYN+ package includes comprehensive sets of Monte Carlo and...
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Martin Balden (GNOI)19/05/2026, 16:20B. Material Erosion, Migration, Mixing, and Dust FormationPoster
Ion cyclotron resonance heating (ICRH) is one of the essential heating systems in fusion devices, and the only mean of depositing energy directly on ions to boost fusion reactions. To maximize the power coupled to the plasma, ICRH antennas, surrounded by protection limiters, must be placed as close as possible to the plasma. If the antenna is too far, little power can be injected, but if it is...
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Pyry Virtanen (Aalto University)19/05/2026, 16:20B. Material Erosion, Migration, Mixing, and Dust FormationPoster
ERO2.0 simulations of the limiter phase in the JET ITER-like wall (JET-ILW) predict nickel to erode primarily from the low-field side (LFS) midplane of the inconel 625 vacuum vessel wall due to charge-exchange neutrals. Inconel is a nickel alloy, mixed with iron and chromium. The sputtered nickel ionizes mostly in the LFS scrape-off layer and is transported by the plasma flows towards the...
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160. 2.042 Thermal transition of W-on-W adhesion from van der Waals interactions to metallic bondingMarco De Angeli (Institute for Plasma Science and Technology - CNR Italy)19/05/2026, 16:20B. Material Erosion, Migration, Mixing, and Dust FormationPoster
The adhesion of dust on plasma-facing components (PFCs) plays a pivotal role in remobilization, wall mechanical impacts, resuspension during loss-of-vacuum accidents, collection activities and removal techniques [1]. Theoretical evaluations are possible with: (i) the van der Waals approach with adhesion assumed to emerge from the cumulative interaction between instantaneously induced...
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Arkadi Kreter (Forschungszentrum Jülich)19/05/2026, 16:20B. Material Erosion, Migration, Mixing, and Dust FormationPoster
The new ITER baseline foresees boronizations for reliable plasma operations in the initial stages of experimental campaigns. However, boron can enhance the fuel retention in the wall and decrease the availability of ITER. Therefore, it is essential to understand the erosion and redeposition mechanisms of boron and its codeposition with hydrogen isotopes.
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We performed studies of boron erosion... -
Daniel Gautam19/05/2026, 16:20B. Material Erosion, Migration, Mixing, and Dust FormationPoster
Oxygen (O), as a common medium-Z impurity in vacuum vessels, is one of the main concerns for magnetic confinement fusion devices, in part due to its high chemical reactivity and its potential to act as seed for sputtering of high-Z materials. For devices with full tungsten (W) walls for which the adsorption of O is low relative to other plasma-facing materials (PFM), wall conditioning...
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Daniel Gautam19/05/2026, 16:20B. Material Erosion, Migration, Mixing, and Dust FormationPoster
Neon (Ne) is considered to be used in magnetic confinement fusion devices for radiative plasma edge cooling and reduction of divertor heat loads. However, uncontrolled release of medium-Z impurities such as Ne will degrade plasma performance and lead to erosion of plasma-facing materials (PFM) by sputtering of high-Z elements. It is thus important to understand the Ne-retention behaviour in...
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Antti Hakola (VTT)19/05/2026, 16:20B. Material Erosion, Migration, Mixing, and Dust FormationPoster
The new baseline of ITER foresees tungsten (W) as the sole plasma-facing material in the reactor vessel. To ensure proper conditioning of the all-W device, in particular for controlling oxygen levels in the plasma and enabling reliable start-up of the experimental operations, regular boronizations have been proposed. An unavoidable consequence of boronizations, however, will be the formation...
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Andrea Uccello (Consiglio Nazionale delle Ricerche, Istituto per la Scienza e Tecnologia dei Plasmi (CNR-ISTP))19/05/2026, 16:20B. Material Erosion, Migration, Mixing, and Dust FormationPoster
As part of ITER’s 2023 re-baselining, the first-wall material was changed from beryllium to tungsten. The absence of the beneficial ability of Be to getter low-Z impurities like oxygen will be compensated by covering the armour tiles with a boron layer of 10-100 nm (boronisation). Broadening the understanding of physics behind B erosion and re/co-deposition is a top priority for ITER to...
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Sean Kosslow (University of Tennessee - Knoxville)19/05/2026, 16:20B. Material Erosion, Migration, Mixing, and Dust FormationPoster
Boron (B) layers deposited on the PFCs erode quickly off of surfaces that receive high incident ion fluxes such as divertor targets, RF antenna protection limiters, and startup limiters. However, main wall surfaces away from the ion flux areas or in areas shadowed by other components may sustain their layers for significantly longer. To study the short time scale erosion and migration of B...
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Dr Prashant Dwivedi (Czech Technical University in Prague)19/05/2026, 16:20B. Material Erosion, Migration, Mixing, and Dust FormationPoster
Tungsten (W) plasma-facing components in magnetic-confinement fusion are simultaneously exposed to intense helium (He) implantation and to high-velocity dust remobilization events. While each driver is known to degrade W surfaces, their combined impact remains insufficiently constrained because He implantation generates a spectrum of subsurface defect morphologies (e.g., bubbles, bubble...
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Juri Romazanov (FZJ)19/05/2026, 16:20B. Material Erosion, Migration, Mixing, and Dust FormationPoster
We present ERO2.0 simulations that reproduce the experimentally observed similarity in erosion rates between boron nitride–boron (B-BN) pebbles and solid boron (B). Low-Z plasma-facing materials like B are attractive for fusion reactors due to their low core plasma radiation compared to high-Z materials such as tungsten. However, pure B erodes and evaporates rapidly, limiting component...
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Jort van Kesteren (DIFFER)19/05/2026, 16:20B. Material Erosion, Migration, Mixing, and Dust FormationPoster
The recent decision from ITER to replace the beryllium first wall with tungsten requires boronization on the first wall to capture sufficient oxygen and minimise plasma cooling caused by high-Z plasma material interactions. The deposited layer thickness and frequency of boronizations are critical, since redeposition in remote locations leads to thick deposits, potentially causing flaking and...
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Gakushi Kawamura (National Institutes for Quantum Science and Technology)19/05/2026, 16:20D. Wall Conditioning and Tritium Removal TechniquesPoster
Wall conditioning is an essential technique to control particle recycling on the wall surfaces and to realize stable discharges of fusion plasma. In recent large devices, superconducting coils are installed for high performance and long discharges, and Wall Conditioning with Electron Cyclotron resonance (ECWC) is planned as an inter-shot wall conditioning to avoid frequent de-energization of...
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Dr Céline MARTIN (Aix Marseille Univ, CNRS, PIIM, UMR 7345)19/05/2026, 16:20D. Wall Conditioning and Tritium Removal TechniquesPoster
Following ITER re-baseline and the replacement of beryllium by tungsten (W), there is a need for assessing the efficacy of diborane glow discharge boronization systems [1,2]. Such systems are regularly used in full-W tokamaks such as ASDEX upgrade and WEST as standard conditioning method.
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To support ITER research into fuel retention and lifetime of boron layers, a non-uniform boronization was... -
Joseph Snipes (Princeton Plasma Physics Laboratory)19/05/2026, 16:20D. Wall Conditioning and Tritium Removal TechniquesPoster
Following the decision to begin ITER operation with a full tungsten first wall and divertor, it became necessary for ITER to also include boron wall conditioning techniques to avoid excessive influx of tungsten into the plasma that would radiate away the plasma stored energy and make the path to long pulse discharges up to Q=10 quite challenging. As a result, Glow Discharge Boronization (GDB)...
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Sanah Hussain (GNOI)19/05/2026, 16:20D. Wall Conditioning and Tritium Removal TechniquesPoster
Accurate wall temperature monitoring is essential for the safe operation of magnetic confinement fusion devices like ITER, and is routinely performed using infrared (IR) thermography. However, the fully metallic nature of the ITER First Wall (FW) introduces strong reflective effects, where hot optics and thermal scene parasitic light and variable emissivity of surfaces can lead to significant...
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Huace Wu (Forschungszentrum Jülich)19/05/2026, 16:20D. Wall Conditioning and Tritium Removal TechniquesPoster
Boronization is used in present-devices as wall conditioning technique to getter oxygen, reduce other intrinsic impurities in the vessel, and control the hydrogen recycling as well as improving plasma performance. The technique is also foreseen as reference wall conditioning method for the new ITER baseline with full-tungsten (W) wall. However, the effectiveness of the deposited Boron (B)...
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Prof. Hiroaki Nakamura (National Institute for Fusion Science)19/05/2026, 16:20D. Wall Conditioning and Tritium Removal TechniquesPoster
Carbon-based plasma-facing materials (PFMs) have been regarded as attractive candidates for fusion reactors owing to their high compatibility with plasma performance and favorable thermal properties. However, concerns over tritium retention and material activation have led to the adoption of metallic PFMs in recent devices. In contrast, experiments on the QUEST device identified a hydrogen...
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Braden Moore (University of Illinois Urbana-Champaign)19/05/2026, 16:20D. Wall Conditioning and Tritium Removal TechniquesPoster
Liquid lithium plasma-facing components (PFCs) present several advantages for fusion applications, including enhanced plasma performance, protection of underlying structural materials, and mitigation of transient melting phenomena associated with solid PFCs. As a low atomic number (low-Z) material, lithium exhibits strong gettering capabilities and enables operation in a low-recycling plasma...
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Henri Kuivasniemi (GNOI)19/05/2026, 16:20F. Edge and Divertor Plasma PhysicsPoster
In JET ITER-like-wall low-confinement mode plasmas the radial scrape-off layer (SOL) measured profiles of electron temperature and density at the low-field side (LFS) midplane and the ion fluxes to the LFS target plates were the same, within the uncertainties of the measurements, for the same volume-averaged core density profiles, independently of the LFS strikepoint connected to a...
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Victoria Winters (University of Greifswald/Max Planck Institute for Plasma Physics)19/05/2026, 16:20F. Edge and Divertor Plasma PhysicsPoster
Achieving high plasma density near the divertor target in magnetically confined fusion devices is beneficial for two main operational objectives: firstly, the high densities lead to high neutral densities near the pumping duct, allowing for efficient particle exhaust. Secondly, it allows for significant radiation (heat exhaust) in the SOL with minimal impurity concentration ($P_{rad}∝n_e^2...
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Mathias Groth (Aalto University, Espoo, Finland)19/05/2026, 16:20F. Edge and Divertor Plasma PhysicsPoster
Standalone EIRENE simulations of neutral deuterium emission across the DIII-D low-field side (LFS) divertor target accurately predict the measured Lyman and Balmer series radiative emission in both attached and detached divertor conditions when constrained by the measured 2D Divertor Thomson Scattering (DTS) electron temperature (Te) and (ne), and Langmuir probe (LP) ion current density. A...
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Linnéa Björk (MPPL)19/05/2026, 16:20F. Edge and Divertor Plasma PhysicsPoster
The W7-X stellarator is an experimental device to study the reactor relevance of this concept. Its complex three-dimensional geometry makes full plasma characterization challenging, particularly in the scrape-off layer (SOL) where plasma behaviour can be highly localized. Understanding transport and physics in this region is essential for reactor design. Therefore, a Bayesian inference...
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Sebastian Draeger (MPPL)19/05/2026, 16:20F. Edge and Divertor Plasma PhysicsPoster
The divertor plays a crucial role in plasma and particle exhaust.
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After heating the surrounding plasma, He ions need to be diverted through the scrape-off layer into the divertor chamber.
Here plasma neutralizes on divertor targets in high-flux regions, known as strike lines.
In Wendelstein 7-X (W7-X) this exhaust is accomplished via an island divertor, where resonant magnetic islands... -
Hugo Corvoysier (CEA, IRFM, F-13108 Saint Paul-lez-Durance, France)19/05/2026, 16:20F. Edge and Divertor Plasma PhysicsPoster
Handling and mitigating heat fluxes to plasma-facing components remains one of the primary challenges for magnetic fusion devices. In future high-field compact machines relying on high-temperature superconducting coils (e.g., SPARC [J. D. Lore 2024]), the heat-flux decay length $\lambda_q$, which characterizes the width of the Scrape-Off Layer (SOL), is predicted to be critically small...
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Joey Louwe (MPPL)19/05/2026, 16:20F. Edge and Divertor Plasma PhysicsPoster
Modern large-scale magnetic confinement fusion devices use divertors to optimize particle and heat exhaust. At the Wendelstein 7-X stellarator (W7-X), this is achieved with an Island Divertor concept, where magnetic islands guide particles and heat along field lines to dedicated target plates. Given the 3D-nature of the island divertor geometry, a large part of the island needs to be diagnosed...
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Heinke Frerichs (University of Wisconsin - Madison)19/05/2026, 16:20F. Edge and Divertor Plasma PhysicsPoster
Particle and power exhaust remains one of the major challenges for burning plasma operation in next generation tokamaks and stellarators. Plasma detachment via impurity seeding is a possible solution which has been widely explored on present devices and which is the default approach adopted on ITER. For future devices, predictive modeling is the only tool available both for divertor design and...
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Dr Hiroyuki Takahashi (Tohoku University)19/05/2026, 16:20F. Edge and Divertor Plasma PhysicsPoster
0ne of the major challenges on the pathway to fusion power plants is safe control of large plasma heat load to the strike points. To keep the plasma heat load below acceptable limits, fusion reactors are expected to operate in detached divertor regime. The detached divertor is facilitated by electron-ion recombination and molecular activated recombination (MAR). Although experimental studies...
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Kevin Andrea Siever (MPPL)19/05/2026, 16:20F. Edge and Divertor Plasma PhysicsPoster
The leading concept for power exhaust in stellarators is the island-divertor configuration. At Wendelstein 7-X (W7-X) the scrape-off layer (SOL) of the standard magnetic configuration is characterized by a 5 island-chain. The islands topology and their interaction with the divertor targets lead to a complex behavior of the impurity radiation structure. Moreover, the more dominant bi-normal...
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Chanyeong Lee (Korea Advanced Institute of Science and Technology)19/05/2026, 16:20F. Edge and Divertor Plasma PhysicsPoster
Plasma detachment via impurity seeding is the most common and widely explored solution for the heat exhaust problem to date. The physics of this process has been usually studied with dedicated 2D edge transport codes such as SOLPS-ITER. However, scenario development and testing of control schemes with rapid pulse design simulators on future devices requires reduced models that run on much...
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Roland Friedl (University of Augsburg, AG Experimentelle Plasmaphysik)19/05/2026, 16:20F. Edge and Divertor Plasma PhysicsPoster
Spectroscopy in the vacuum-ultraviolet (VUV) range, i.e. below 200$\,$nm, gives access to the resonant transitions of atomic (Lyman series) and molecular hydrogen (Lyman and Werner bands). In order to get insight into the relevance of molecules and their recombination in edge plasmas, intensity calibrated emission spectroscopy is a valuable diagnostic. In the VUV spectral range, however,...
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Kaushlender Singh (École Polytechnique Fédérale de Lausanne (EPFL), Swiss Plasma Center (SPC), CH-1015 Lausanne, Switzerland)19/05/2026, 16:20F. Edge and Divertor Plasma PhysicsPoster
Understanding and evaluating particle and energy exhaust in the divertor and scrape-off layer (SOL) regions of a tokamak are essential for the sustainable operation of future fusion devices such as ITER. Cross-field transport in the SOL is known to be dominated by intermittent, elongated convective structures called filaments or blobs. In this study, filament-induced cross-field heat and...
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Sean Ballinger (Commonwealth Fusion Systems)19/05/2026, 16:20F. Edge and Divertor Plasma PhysicsPoster
The SPARC tokamak is projected to have high unmitigated heat fluxes to the divertor plasma-facing components, with q|| up to 10 GW/m2 in H-mode, due to its high magnetic field and current (8.7 MA, 12.2 T). Type-I ELMs will cause unacceptable energy fluence on the target for routine operation due to the high pedestal pressures in H-Mode conditions. The separatrix density is an important...
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Shifeng Mao (University of Science and Technology of China (CN))19/05/2026, 16:20F. Edge and Divertor Plasma PhysicsPoster
The tokamak divertor is subjected to huge heat load, including both the transient heat load due to the edge localized modes (ELMs) and steady-state heat load in between ELMs. Exploring the edge plasma solution compatible with the high-performance plasma is critical for the fusion reactors. Numerical simulations are indispensable for both understanding the edge plasma physics and predicting the...
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Daniil Ryndyk (FZJ)19/05/2026, 16:20F. Edge and Divertor Plasma PhysicsPoster
Wendelstein 7-X (W7-X) operates with carbon-fiber composite (CFC) plasma-facing components (PFC) forming the island divertor used for particle and power exhaust. Erosion of PFCs leads to an influx of carbon (C) into the edge plasma where C radiation significantly cools down the divertor in the applied hydrogen plasmas. Rising the radiation in the divertor by hydrogen fueling and/or impurity...
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Shogo Otsuka (Tohoku Univ.)19/05/2026, 16:20F. Edge and Divertor Plasma PhysicsPoster
One of the most important subjects in detached divertor plasma studies is reliable diagnostics of the electron density ($n_e$) and temperature ($T_e$). He I line-intensity-ratio-method (LIR-method), based on a visible spectroscopy and a collisional-radiative (CR) analysis, offers a non-invasive measurement of these parameters. When this method is applied to plasmas with high neutral densities,...
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Paolo Innocente (Institute for Plasma Science and Technology, CNR, 35127 Padova, Italy)19/05/2026, 16:20F. Edge and Divertor Plasma PhysicsPoster
To ensure an operating regime compatible with its tungsten divertor, ITER must operate at least in a partially detached state. Considering the required level of power crossing the separatrix ($P_{SOL}$) to sustain H-mode, such a partially detached state will be achieved through strong radiative power losses obtained via extrinsic (seeded) impurities. However, impurities can also influence...
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Mark Cornelissen (Eindhoven University of Technology)19/05/2026, 16:20I. Plasma Edge and First Wall DiagnosticsPoster
Plasma flows are fundamental in understanding various aspects of the power exhaust in fusion devices, including helium exhaust, impurity transport, detachment processes, and distribution of the diverted heat flux [1-3]. A comprehensive and validated understanding of the plasma flows is required for evaluating and optimizing power exhaust strategies [4,5].
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A multi-spectral coherence imaging... -
Tomás Sousa (University of Basel)19/05/2026, 16:20I. Plasma Edge and First Wall DiagnosticsPoster
The ITER Wide Angle Viewing System (WAVS) relies on in-vessel metallic mirrors to transport optical signals from the plasma to out-of-vessel diagnostics [1]. Under the conditions of ITER, energetic plasma particles induce sputtering of plasma-facing components, and the resulting sputtered material can re-deposit on these mirrors, resulting in reflectivity degradation [2, 3].
In-situ plasma...
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Laura Dittrich (IPP)19/05/2026, 16:20I. Plasma Edge and First Wall DiagnosticsPoster
Erosion, re- and co-deposition processes in Wendelstein 7-X (W7-X) lead to the formation of deposits on plasma-facing components (PFCs). Owing to the carbon-based wall-tiles, these deposits are carbon-dominated including hydrocarbons, oxides,and boron co-deposits. Characterizing these deposits is essential for understanding material migration and fuel retention.
A handheld spectroscopic...
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Arseniy Kuzmin (Kyoto University, Kyoto, Japan)19/05/2026, 16:20I. Plasma Edge and First Wall DiagnosticsPoster
Boron remains a key material for real-time wall conditioning in fusion devices due to its strong gettering properties and its impact on impurity control and hydrogen recycling. Previous LHD experiments have identified boron monohydride (BH) emission as a sensitive indicator of surface processes during boron powder injection, with localized signatures near the divertor and rotational...
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Keisuke Fujii (Oak Ridge National Laboratory)19/05/2026, 16:20I. Plasma Edge and First Wall DiagnosticsPoster
A novel spectroscopic technique has been used to perform the direct measurement of impurity poloidal flow in the DIII-D divertor. Particle dynamics in the open-field-line scrape-off-layer (SOL) and divertor, to which both parallel and perpendicular transport contribute, are critical for predicting heat and particle loads on plasma-facing components. While the parallel component of impurity...
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Pavel Veis (FMPI, Comenius University, Bratislava, Slovakia)19/05/2026, 16:20I. Plasma Edge and First Wall DiagnosticsPoster
Laser-Induced Breakdown Spectroscopy (LIBS) is a key diagnostic for analysing plasma-facing components in fusion devices [1], where erosion, migration, redeposition and fuel retention produce complex multi-element layers containing Be, W, Mo, H/D/T isotopes and various impurities [2,3]. Accurate characterisation of these layers is essential for understanding material migration, surface...
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Shin Kajita19/05/2026, 16:20I. Plasma Edge and First Wall DiagnosticsPoster
While the helium line intensity ratio method has been used to measure electron, ne, and temperature, $T_e$, by combining measured line intensities with a collisional radiative model (CRM) [1], one of its difficulties is to include the photon transport and metastable atom transport. A machine learning (ML) approach has been considered as an alternative method to measure $n_e/T_e$ from the line...
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Shweta Soni (IPP)19/05/2026, 16:20I. Plasma Edge and First Wall DiagnosticsPoster
Monitoring and detection of deuterium (D) retention in plasma-facing components in a tokamak is essential for safety and fuel management. In this work, we present femtosecond laser-induced ablation coupled to quadrupole mass spectrometry (fs-LIA-QMS) to investigate D depth profiles in Fe–Zr/Y+D–Fe multilayer samples (each layer ~1 µm) prepared on Si substrates. Fs-LIA-QMS combines ultrafast...
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Hirohiko Tanaka (Nagoya University)19/05/2026, 16:20I. Plasma Edge and First Wall DiagnosticsPoster
Reducing the enormous heat flux on the divertor target is key to realizing future fusion reactors. One promising approach is to increase the neutral gas pressure near the divertor to promote strong plasma recombination. This leads to a detached plasma state, in which heat and particle fluxes to the target are significantly reduced. However, current understanding is insufficient to reliably...
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Georg Schlisio (IPP HGW)19/05/2026, 16:20I. Plasma Edge and First Wall DiagnosticsPoster
The diagnostic residual gas analyzer (DRGA) at Wendelstein 7-X (W7-X) provides remote measurements of the exhaust gas composition sampled from the sub-divertor region. A new compact time-of-flight mass spectrometer has been installed and operated routinely during the latest operation campaign OP2.3. It records full mass spectra, enabling comprehensive monitoring of exhaust-gas dynamics. The...
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Nina Mihajlov (University of Illinois, Urbana-Champaign)19/05/2026, 16:20J. Plasma Exhaust and Plasma Material Interactions for Fusion ReactorsPoster
Lithium (Li) as a plasma facing material is of great interest due to its ability to retain and pump recycled reactive atoms, decrease instabilities and increase plasma performance. The most recent Li experimental campaign in the HIDRA device at the University of Illinois, Urbana-Champaign, named the Hydrogen Absorption and Desorption Experiment in a Stellarator (HADES) campaign, has shown...
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Aaliyah Zuniga (GNOI)19/05/2026, 16:20J. Plasma Exhaust and Plasma Material Interactions for Fusion ReactorsPoster
High-density (99.8%) electron beam powder bed fusion (EB-PBF) tungsten (W) has been successfully manufactured and deployed in plasma material interaction investigations that included DIII-D tokamak and Tritium Plasma Experiment (TPE) exposures. Since the tailored microstructure of EB-PBF W is fundamentally different from conventionally manufactured W, critical knowledge gaps were addressed...
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Thomas Morgan (DIFFER)19/05/2026, 16:20J. Plasma Exhaust and Plasma Material Interactions for Fusion ReactorsPoster
The COMPASS-Upgrade tokamak will be a high field compact device (R = 0.9 m, Bt = 5 T, Ip = 2 MA, tflattop = 2-10 s) capable of studying diverse magnetic configurations at high plasma densities [1]. The small machine size, high B and relatively high heating power means that scrape-off layer widths are predicted to be small (λq~0.6–1.2 mm), and attached power densities up to 100 MW m-2 could be...
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Zhaofan Wang (University of Science and Technology of China)19/05/2026, 16:20J. Plasma Exhaust and Plasma Material Interactions for Fusion ReactorsPoster
In magnetic confinement nuclear fusion devices, Tungsten (W) is considered the most promising plasma-facing materials (PFMs) for divertor, which will be exposed to high-energy neutron irradiation, high flux plasma irradiation at high temperatures (up to 1200 °C during steady-state operation). High-energy neutron irradiation can directly generate dislocation loops through collision cascades, or...
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laura Laguardia (ENEA-CNR)19/05/2026, 16:20J. Plasma Exhaust and Plasma Material Interactions for Fusion ReactorsPoster
High-energy plasma interacting with plasma-facing components (PFCs) causes surface damage (e.g., vaporization, sputtering) via intense heat and particle fluxes, compromising reactor lifetime, performance, and safety. Effective PFCs require properties like low sputter yield, high melting point, thermal conductivity, moderate activation, and low gas permeation. Meeting diverse, location-specific...
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Andrea Mastrogirolamo (Politecnico di Milano)19/05/2026, 16:20J. Plasma Exhaust and Plasma Material Interactions for Fusion ReactorsPoster
Understanding helium-induced plasma-surface interaction (PSI) on tungsten is essential for quantifying divertor erosion and impurity sourcing in magnetic confinement fusion devices, as He will inherently accumulate as a fusion ash. Experiments at ASDEX Upgrade have provided erosion, deposition and morphology data for He-based L- and H-mode discharges [1,2]. Here we present a modelling study to...
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Mr Haoxuan Yu (University of Illinois Urbana-Champaign)19/05/2026, 16:20J. Plasma Exhaust and Plasma Material Interactions for Fusion ReactorsPoster
Helium is a byproduct of the DT fusion reaction and if not removed quickly enough will pose a real issue as a contaminant of the fusion plasma. Helium is difficult to remove and so finding ways of removing it sufficiently quickly is of importance. Recent results in HIDRA and MAGNUM-PSI have shown that liquid lithium can certainly do the pumping and the FLIER results from the early 2000’s show...
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MARIA MORBEY (GNOI)19/05/2026, 16:20J. Plasma Exhaust and Plasma Material Interactions for Fusion ReactorsPoster
Liquid metals, and lithium (Li) in particular, are increasingly considered strong candidates for next-generation divertor concepts in fusion reactors due to their excellent power-handling capabilities and self-healing behavior. However, lithium’s high affinity for hydrogen isotopes and its tendency to form stable hydrides introduce important challenges for tritium (T) inventory control and...
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Rahul Rayaprolu (Forschungszentrum Jülich)19/05/2026, 16:20J. Plasma Exhaust and Plasma Material Interactions for Fusion ReactorsPoster
Linear plasma devices can generate steady state long duration plasma and are ideal for lifetime plasma exposure studies on plasma-facing materials (PFM) in a fusion reactor. The plasma exposures are followed by in-situ and ex-situ measurements on surface erosion and fuel retention respectively. Additional possibilities such as sample biasing and sample temperature variation enable a wide...
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Gregory Sinclair (General Atomics)19/05/2026, 16:20J. Plasma Exhaust and Plasma Material Interactions for Fusion ReactorsPoster
A repository storing key performance data collected from integrated material testing on the DIII-D tokamak is being actively developed in collaboration with the Clean Air Task Force Material Database for Fusion (MatDB4Fusion) initiative to aid in material down-selection for commercial fusion reactor deployment. Advancing the technological readiness level of plasma-facing materials (PFMs)...
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Dr Udo von Toussaint (Max-Planck-Institute for Plasmaphysics)19/05/2026, 16:20J. Plasma Exhaust and Plasma Material Interactions for Fusion ReactorsPoster
The interaction of neutral and charged particles with the plasma-facing wall sets the boundary conditions for the confined plasma and is thus essential for important aspects like L-H power transition thresholds or impurity radiation. For example the transition from carbon to tungsten as wall material in ASDEX Upgrade reduced the L-H power threshold by about 25% which has been traced to the...
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Masayuki Tokitani (National Institute for Fusion Science)19/05/2026, 16:20J. Plasma Exhaust and Plasma Material Interactions for Fusion ReactorsPoster
Combined joint method of brazing and diffusion bonding, for between tungsten (W) and Reduced Activated Ferritic/Martensitic (RAFM) steel (W/RAFM steel) with a pure-Cu intermediate layer, was developed. Flat plate type joint sample of W/pure-Cu/RAFM steel with the joint area of 20 × 20 mm² was selected in this experiment, in which W and the 1 mm thick pure-Cu was jointed by brazing with Ni-11%P...
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Chao Yin (University of Science and Technology of China)19/05/2026, 16:20J. Plasma Exhaust and Plasma Material Interactions for Fusion ReactorsPoster
Tungsten (W) is the leading candidate for plasma-facing components in future magnetic confinement fusion reactors due to its high melting point, low fuel retention, excellent thermal conductivity, etc. However, the elevated operating temperatures, high neutron flux and plasma flux expected in devices such as ITER, BEST, and DEMO can accelerate recrystallization, leading to grain boundary...
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Dr Hanns Gietl (Max Planck Institute for Plasma Physics, 85748 Garching, Germany)19/05/2026, 16:20J. Plasma Exhaust and Plasma Material Interactions for Fusion ReactorsPoster
A significant challenge on the path to magnetic confinement fusion power plants is the robust exhaust of power and particles. In particular, plasma‑facing components (PFCs) in the divertor region must endure challenging particle and heat fluxes while simultaneously sustaining damage from fusion‑neutron irradiation. This leads to a progressive degradation of key material properties such as...
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Mr Alessio Villa (Politecnico di Torino)19/05/2026, 16:20J. Plasma Exhaust and Plasma Material Interactions for Fusion ReactorsPoster
Runaway Electrons (REs) generated during disruption events pose a critical challenge for the operation of next-generation fusion devices such as DEMO. The thermal quench causes intense heat and particle loads on plasma-facing components (PFCs), while the current quench can induce a strong toroidal electric field that accelerates electrons to relativistic energies. A detailed understanding of...
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Simon Corah (School of Metallurgy and Materials, University of Birmingham)19/05/2026, 16:20J. Plasma Exhaust and Plasma Material Interactions for Fusion ReactorsPoster
Tungsten (W) is the primary candidate material for plasma-facing components in the fusion divertor. However, the operational limits of conventional W necessitate the development of advanced variants to mitigate issues regarding brittleness and thermal stability. This research focuses on determining how specific material modifications, compositional doping and additive manufacturing (AM),...
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Bianca De Martino (CEA/IRFM)19/05/2026, 16:20J. Plasma Exhaust and Plasma Material Interactions for Fusion ReactorsPoster
The WEST tokamak hosts a comprehensive set of diagnostics dedicated to monitoring heat flux, radiation, impurity transport, and local plasma parameters, providing detailed characterisation of its scrape-off layer (SOL). Among the available diagnostics, mobile Langmuir probes positioned at strategic SOL locations can be equipped with sample holders, enabling controlled exposure of material...
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Ms Emna frikha (Sorbonne Paris Nord University, Laboratory of Process and Materials Sciences, LSPM, CNRS, UPR 3407, F-93430, Villetaneuse, France)19/05/2026, 16:20J. Plasma Exhaust and Plasma Material Interactions for Fusion ReactorsPoster
The trapping of helium in crystal defects in tungsten is one of the mechanisms of bubble nucleation. Due to its low solubility and high mobility, helium tends to accumulate by self-trapping or trapping in defect sites such as dislocations, grain boundaries, and vacancies, leading to bubble formation. When these bubbles come close enough, they can coalesce and form large bubbles. Large bubbles...
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Selanna Roccella (ENEA)19/05/2026, 16:20J. Plasma Exhaust and Plasma Material Interactions for Fusion ReactorsPoster
The first divertor of DTT [1] will accommodate different magnetic configurations while maximizing heat exhaust capability. Therefore, most of its plasma-facing surface is based on ITER-like plasma-facing units (PFUs), consisting of CuCrZr cooling tubes protected with tungsten monoblocks [2]. To intercept the strike points of the reference magnetic configurations (Signe Null, X-Divertor, and...
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Kenta Kawashimo (University of Illinois Urbana-Champaign)19/05/2026, 16:20J. Plasma Exhaust and Plasma Material Interactions for Fusion ReactorsPoster
Liquid lithium (Li) is considered an attractive candidate for Plasma Facing Components (PFC) in magnetic confinement fusion devices due to its high heat and particle exhaust capabilities, self-replenishing property, and potential for confinement improvement. Additive-manufactured structures made of refractory metal, such as tungsten (W), gained interest as solid substrates for Li PFCs to...
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Dr Sangeetha Sasidharan (Max-Planck-Institut für Plasmaphysik, Garching, Germany)19/05/2026, 16:20B. Material Erosion, Migration, Mixing, and Dust FormationPoster
Dust particles are recognized as a significant safety issue in the future fusion devices. When present in large quantities they may create an operational risk for the fusion device. Even small amounts, mobilized during a discharge, can cause additional radiation and influence the plasma performance. Dust particles can be observed by cameras, but these events are hard to interpret. In the...
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Shigetaka Kagaya (Tohoku university, Sendai, Japan)19/05/2026, 16:20F. Edge and Divertor Plasma PhysicsPoster
Excessive heat flux to the divertor plates is one of the most serious issues in magnetic fusion reactors. A detached divertor, in which neutral gas injection enhances radiation and volumetric recombination, is the most promising candidate for mitigating the divertor heat load. Thus integrated divertor simulation codes for future fusion reactors are actively developed. Linear plasma devices,...
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