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Yuchen Xu (University of Science and Technology of China)22/05/2026, 09:50F. Edge and Divertor Plasma PhysicsPoster
Impurity injection is an effective way to control the burst of edge localized modes (ELMs), which have to be avoided due to the severe damages on the plasma-facing components in future fusion reactor. In recent EAST experiments, it has been demonstrated that, large ELMs can be mitigated or even suppressed by neon (Ne) seeding utilizing supersonic molecular beam injection (SMBI) when the Ne...
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Jiafeng He (University of Science and Technology of China)22/05/2026, 09:50F. Edge and Divertor Plasma PhysicsPoster
It is critical to control the heat load onto the divertor target for the future fusion reactor. While the resonant magnetic perturbation (RMP) is proved to be an effective way to control the transient heat load due to the burst of edge-localized modes (ELMs) [1], the distribution of the inter-ELM divertor heat load will be significantly affected simultaneously [2] due to the three-dimensional...
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Xavier Bonnin (ITER Organization)22/05/2026, 09:50F. Edge and Divertor Plasma PhysicsPoster
The SOLPS-ITER code suite [1,2] is one of the main tools used worldwide for tokamak edge modelling. Launched in 2015 and maintained and distributed by the ITER Organization (IO), it was recently extended to a “Wide Grids” version [3], allowing the plasma solver computational domain to extend to the full vacuum vessel and provide a much more detailed description of the interactions between the...
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Tsunehiro Morita (Kyoto University)22/05/2026, 09:50F. Edge and Divertor Plasma PhysicsPoster
In this study, we develop a diagnostic technique to detect detachment onset. The technique utilizes a characteristic feature of the atomic line emission profile in the detached plasma, namely the emergence of atomic line emission peaks near the hydrogen recombination front. Our aim is to establish a simple and robust technique suitable for future fusion reactors. The recombination front is...
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Mr Satoshi TAKAHASHI (Plasma Research Center, University of Tsukuba)22/05/2026, 09:50F. Edge and Divertor Plasma PhysicsPoster
Injecting impurity gases into the divertor region to enhance volumetric recombination and form detached plasmas is a promising approach to mitigate intense divertor heat loads. Understanding the underlying physics of divertor detachment is important for controlling heat and particle fluxes in the divertor while maintaining core plasma performance.
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Molecular activated recombination (MAR) has... -
Kerry Lawson (UKAEA)22/05/2026, 09:50F. Edge and Divertor Plasma PhysicsPoster
An understanding of the behaviour of the D or He fuel used in tokamak discharges is necessary for modelling edge and divertor transport. Despite there being well-established models describing the emission from the H-like fuel, poor agreement is found between JET line-of-sight measurements and Collisional-Radiative (CR) models used to predict their line intensities. Lawson et al. (2024)...
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Nassim Maaziz22/05/2026, 09:50F. Edge and Divertor Plasma PhysicsPoster
The island divertor is the leading exhaust concept in stellarators. Used in W7-X, it has proven to provide density control, stable detachment, and impurity screening [1]. Although a regime with enhanced recycling has been observed in W7-X, moderate neutral pressures of up to 0.18 Pa have been measured so far [2]. Higher recycling conditions are necessary to ensure the reactor-relevance of the...
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Akira TONEGAWA (GNOI)22/05/2026, 09:50F. Edge and Divertor Plasma PhysicsPoster
In the DEMO reactor, the enormous heat flux released from the core to the divertor plasma reaches several times that of ITER. Therefore, research is being conducted on advanced divertors aimed at reducing heat flux by increasing the plasma wetted area under divergent magnetic field and generating detached plasma. It is extremely important to investigate the effect of plasma flow acceleration...
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Vsevolod Soukhanovskii (LLNL)22/05/2026, 09:50F. Edge and Divertor Plasma PhysicsPoster
A snowflake divertor (SFD) is formed by bringing a second X-point into the vicinity of the first, resulting in four divertor legs instead of two. SFD experiments have provided evidence of enhanced transport across the region close to the X-points, resulting in redistributed exhaust power across divertor legs and reduced peak heat fluxes at the targets [1]. Two leading candidates for this...
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Wouter Dekeyser (KU Leuven, Department of Mechanical Engineering)22/05/2026, 09:50F. Edge and Divertor Plasma PhysicsPoster
The ad-hoc description of anomalous transport remains a dominant uncertainty in mean-field plasma edge modeling. In this contribution, we further develop an improved anomalous transport model based on self-consistent time-averaging of the turbulence equations, assuming electrostatic interchange turbulence [1]. This model solves an additional transport equation for the turbulent kinetic energy...
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Prof. Naomichi Ezumi (University of Tsukuba)22/05/2026, 09:50F. Edge and Divertor Plasma PhysicsPoster
Detached plasmas are essential for controlling heat and particle fluxes to the plasma-facing components of magnetic fusion devices. We have studied the fundamental processes during detached plasma operations in the divertor simulation experimental module (D-module), using a variable-angle V-shaped target plate at the end-loss region of the tandem mirror plasma device GAMMA 10/PDX [1,2]....
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Xiuxin Tang (GNOI)22/05/2026, 09:50F. Edge and Divertor Plasma PhysicsPoster
Linear plasma devices employ analogous transport mechanisms to those in tokamaks, The plasma, constrained by magnetic fields, flows axially along field lines toward the target plate, enabling effective simulation of tokamak divertor conditions. The MPS-LD, owing to its simple structure and flexible parameter control, serves as an important experimental platform for investigating boundary...
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Tanmay Macwan (Lawrence Livermore National Laboratory, USA)22/05/2026, 09:50F. Edge and Divertor Plasma PhysicsPoster
Filamentary transport in the small-ELM H-mode regime, with typical loss in the stored energy of ~ 1 – 2%, is investigated in conventional and snowflake divertor (SFD) configurations in MAST-U with fast framing $D_α$ filtered cameras. Small, frequent edge localized modes (ELMs) are important for future fusion devices as they avoid large transient heat fluxes due to type-I ELMs and still prevent...
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Dirk Wünderlich (IPP Garching)22/05/2026, 09:50F. Edge and Divertor Plasma PhysicsPoster
The plasma parameters in the divertor region of fusion devices are highly relevant for characterizing particle and power exhaust in attached and detached regimes or during the injection of impurities. Due to reduced temperatures compared to the core plasma, both atomic and molecular hydrogen can be present in the divertor plasma and, depending on the operational scenario, also isotopes like...
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Jerome Moritz (Université de Lorraine, Institut Jean Lamour, UMR 7198 CNRS, Campus Artem, 2 allée André Guinier, 54011 Nancy, France)22/05/2026, 09:50F. Edge and Divertor Plasma PhysicsPoster
Plasma-facing components (PFCs) primarily made of tungsten face significant lifetime limitations due to neutron embrittlement, dust formation, local melting and cracking, which threatens the high availability required for future fusion power plants [1,2]. Liquid-metal (LM) based PFCs have emerged as a promising route to overcome these limitations thanks to their intrinsic replenishment...
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Richard Christian Bergmayr (IPP Garching)22/05/2026, 09:50F. Edge and Divertor Plasma PhysicsPoster
Divertor detachment is a promising solution to the heat exhaust problem in future fusion devices by reducing the heat load onto divertor target plates$^1$. During the detachment process a neutral gas layer builds up in-between the plasma and the divertor plates through recombination reactions.
Molecular assisted recombination (MAR) is discussed to be among the dominant volume recombination...
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Floris Scharmer (IPP Greifswald)22/05/2026, 09:50F. Edge and Divertor Plasma PhysicsPoster
The Wendelstein 7-X (W7-X) stellarator experiment uses the island divertor concept for power and particle exhaust. In the most studied configurations, the scrape-off layer (SOL) includes a chain of five islands (m/n = 5/5) around the core. To characterize the SOL, different toroidally separated diagnostics view separate islands. The five-fold toroidal symmetry is typically used to combine...
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Rick van Schaik (GNOI)22/05/2026, 09:50F. Edge and Divertor Plasma PhysicsPoster
Achieving reliable power production in future tokamak reactors requires operating
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regimes that simultaneously deliver high fusion plasma performance and maintain
divertor and first-wall particle and heat-fluxes within material limits. The plasma core
and the scrape-off layer (SOL) regions cannot be decoupled for predictive scenario
development. Integrated modelling frameworks... -
Yinghan Wang (EPFL Swiss Plasma Center)22/05/2026, 09:50F. Edge and Divertor Plasma PhysicsPoster
To obtain high fusion performance and satisfy the first wall material limit in future fusion devices, increasing effort has been made to develop and investigate high-confinement no-ELM (Edge Localized Mode) and small-ELM scenarios. Among them, recently, the X-point radiator (XPR) regime has been developed in multiple devices, including the TCV tokamak, and shows promising ELM suppression...
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Maxim Umansky (LLNL)22/05/2026, 09:50F. Edge and Divertor Plasma PhysicsPoster
In the boundary of magnetic fusion devices, plasma is strongly coupled with recycling
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neutrals. Consequently, an integrated model for fusion boundary transport must encompass
neutral physics. A recently proposed propagator-based approach has the potential to
dramatically enhance the accuracy and efficiency of neutral transport modeling in plasma,
across the range of neutral collisionality... -
Kota TAKEDA (Nagoya University)22/05/2026, 09:50F. Edge and Divertor Plasma PhysicsPoster
In detached divertor experiments, impurity gas injection used to achieve detachment has been reported to cause core plasma cooling near the X-point and, in some cases, radiative collapse. These adverse effects have been attributed to the approach of the recombination front toward the X-point, highlighting the need to establish a technique for controlling the recombination front...
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Kwan Chul Lee (KFE)22/05/2026, 09:50F. Edge and Divertor Plasma PhysicsPoster
In the plasma physics, the momentum exchange by charge exchange reactions between plasma ions and boundary neutrals has been underestimated. Lacking of understanding this important mechanism is one of main causes of the complication in the field of plasma surface interaction. When there is magnetic field, perpendicular component of momentum exchange can generate current and the electric field,...
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Sergei Makarov (Proxima Fusion GmbH, Flößergasse 2, 81369 Munich, Germany)22/05/2026, 09:50F. Edge and Divertor Plasma PhysicsPoster
Stellarators are a promising candidate for steady-state fusion power plants, and recent achievements on Wendelstein 7-X (W7-X) have further strengthened this prospect. A key determinant of reactor viability is the performance of the divertor, which governs impurity control and particle exhaust. While W7-X has demonstrated excellent heat-flux mitigation and steady-state capabilities, it has not...
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Abdourahmane Diaw (Oak Ridge National Laboratory)22/05/2026, 09:50F. Edge and Divertor Plasma PhysicsPoster
Edge plasma simulations with SOLPS-ITER are expensive and sensitive to initialization, especially when spanning wide parameter ranges or tailoring to specific discharges. We present a reduced-modeling workflow that combines (i) warm starts via nearest-neighbor initialization from a KD-tree [1] of converged runs and (ii) learned surrogates for rapid prediction. The KD-tree selects a converged...
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George Wilkie (PPPL)22/05/2026, 09:50F. Edge and Divertor Plasma PhysicsPoster
The transport of neutral atoms and molecules produced from gas puff and the wall recycling process is a critical aspect of the core-edge integration challenge. Because of this, predicting the evolution of edge plasma profiles from simulation requires coupling to self-consistent predictions of the neutral gas. The Monte Carlo method is the most widely-used kinetic method for doing so. Coupling...
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Robert James Davies (MPPL)22/05/2026, 09:50F. Edge and Divertor Plasma PhysicsPoster
The most mature stellarator divertor concept is the island divertor (such as used by Wendelstein 7-X [1]), in which a spatially large magnetic island chain diverts exhausted plasma onto plasma-facing components (PFCs). Despite its maturity, there remain fundamental open questions about how island properties affects edge transport and divertor performance, and how this understanding can be...
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Eunnam Bang (Korea Insutitute of Fusion Energy)22/05/2026, 09:50F. Edge and Divertor Plasma PhysicsPoster
A Langmuir probe (LP) system, designed to measure basic plasma parameters and their poloidal profiles, was installed in the upgraded tungsten divertor of KSTAR [1]. Since the KSTAR 2023 campaign, temporal ion saturation currents have been measured in the lower divertor region by applying a negatively DC-bias of -240 V to the LP using batteries, with a DAQ sampling frequency of 200 kHz. As the...
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Kay Schutjes (DIFFER)22/05/2026, 09:50F. Edge and Divertor Plasma PhysicsPoster
One of the biggest challenges of a reliable fusion reactor is the handling of large heat and particle loads on the divertor wall. Key to reducing these loads is plasma detachment, in which a large range of processes occur between the plasma and the neutral background [1,2].
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Molecular processes dominate the plasma dynamics, which is why molecules are often studied in divertor research [1,2].... -
Annika Lisa Stier (MPPL)22/05/2026, 09:50F. Edge and Divertor Plasma PhysicsPoster
A notable recent success of the island-diverted stellarator Wendelstein 7-X is the achievement of stable detached operation. However, central processes involved in detachment access and detached operation of stellarators still need to be fully understood to explain the observed phenomena and improve the design of future machines.
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Shedding light on these mechanisms is the aim of the simulation... -
David Coster (MPG-IPP)22/05/2026, 09:50F. Edge and Divertor Plasma PhysicsPoster
When modelling the behaviour of current and future tokamaks, the core plasma is often treated separately from the edge/SOL, with different classes of codes used, with weak on non-existent coupling between the models. This work covers efforts to ensure consistency between the modelling of these separate regions by coupling a code suite describing the core plasma (ETS-PAF, a 1.5D core transport...
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Elias Waagaard (MPPL)22/05/2026, 09:50F. Edge and Divertor Plasma PhysicsPoster
Heat exhaust remains a critical challenge for stellarator-based fusion reactors, from experimental machines like W7‑X to reactor candidates such as SQuID. Although significant progress has been made in tokamak divertor physics, including promising regimes such as detachment and X-point radiators (XPR), the extension of these solutions to the inherently three-dimensional stellarator geometry...
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David Bold (IPP Greifswald)22/05/2026, 09:50F. Edge and Divertor Plasma PhysicsPoster
For the design of future experimental devices as well as for the first fusion devices, reliable simulation of the plasma in the scrape-off layer (SOL) is of significant importance. The current state of the art plasma code for stellarator geometries, EMC3-Eirene, is however showing significant disagreement compared to experimental observations [1]. The discrepancies might be explained by...
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Jonathan Roeltgen (ExoFusion)22/05/2026, 09:50F. Edge and Divertor Plasma PhysicsPoster
The full-f, gyrokinetic edge and scrape-off-layer turbulence code GENE-X has been coupled with the Monte Carlo neutral code Eirene. A kinetic treatment of the neutrals was chosen for the improved accuracy over fluid neutrals. This is particularly important for low collisionality regimes expected in reactors. It is impractical to call Eirene every GENE-X timestep, so the neutral source won’t...
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Hoiyun Jeong (Korea Advanced Institute of Science & Technology)22/05/2026, 09:50F. Edge and Divertor Plasma PhysicsPoster
Analyzing charged particle transport near a magnetic X-point in the presence of neutral species is crucial for understanding and controlling tokamak plasmas. To study plasmas in a similar environment, a steady-state, low-temperature plasmas are generated in the MAgnetic X-poInt siMUlator System (MAXIMUS) [1] using a DC-heated cathode. Langmuir probes are utilized to obtain spatially resolved...
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Bridget McGibbon (CEA)22/05/2026, 09:50F. Edge and Divertor Plasma PhysicsPoster
Mean-field fluid edge codes are widely used for planning operations of magnetic fusion devices. Turbulence, a key factor in edge transport, is represented in these codes via diffusion coefficients tuned to match the Scrape-Off Layer (SOL) power fall-off length to existing experimental scaling laws, which are derived from attached plasmas. However, experimental results indicate that...
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Kateřina Hromasová (Institute of Plasma Physics of the Czech Academy of Sciences)22/05/2026, 09:50G. Power Exhaust, Plasma Detachment and Heat Load ControlPoster
Faithful simulations of the tokamak edge plasma, particularly in view of detachment access, are crucial for the design of future fusion reactors. The COMPASS Upgrade tokamak, currently under construction at IPP CAS, Prague, will feature reactor-relevant magnetic fields and target energy fluxes. [1] Previously, predictive SOLPS-ITER [2] simulations have been presented of two COMPASS-U H-mode...
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Mr Jack Flanagan (University of Liverpool)22/05/2026, 09:50G. Power Exhaust, Plasma Detachment and Heat Load ControlPoster
Transient events such as ELMs, sawteeth and H-L back-transitions are inevitable in some form in next step reactor scale tokamaks. Such transients lead to heat fluxes on divertor target tiles which risk cracking and further damage [1, 2]. Mitigation of these fast transient heat fluxes has been shown to be possible in part by increasing neutral gas pressure in the detachment cloud [3, 4] and by...
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Fabio Federici (ORNL)22/05/2026, 09:50G. Power Exhaust, Plasma Detachment and Heat Load ControlPoster
In a fusion power plant it is paramount to control the heat flux reaching the targets. Most of the exhaust heat flux is directed to the outer leg, that hence is often the main focus, but for increasing machine size a correct characterization of the heat flux on the inner target is important, even more for spherical tokamaks as the inner target wetted area is more limited.
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Previous studies on... -
Joseph Bryant (Tokamak Energy Ltd)22/05/2026, 09:50G. Power Exhaust, Plasma Detachment and Heat Load ControlPoster
Recent experiments on ST40 have begun to explore the X-point radiator (XPR) regime in H-mode discharges, with modelling support via SOLPS-ITER. Previous studies on TCV, AUG, WEST, and JET suggest that the XPR regime offers an operating space which reduces divertor heat loads while maintaining good core confinement through the introduction of a stable impurity radiation front above the X-point...
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Dr Giulio Rubino (a ISTP-CNR, via Amendola 122/D, Bari, 70126, Italy)22/05/2026, 09:50G. Power Exhaust, Plasma Detachment and Heat Load ControlPoster
The Divertor Test Tokamak facility (DTT) is designed to investigate power exhaust in fusion reactor-relevant conditions. The schedule of the different operational phases foresees an increase in the installed auxiliary power up to the final full power level. In the very early phase A, the standard single Null (A-SN) plasma scenario is defined by reduced parameters: $B_T=3T$, $I_p=2MA$, and...
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Reina Miyauchi (Plasma Research Center, University of Tsukuba)22/05/2026, 09:50G. Power Exhaust, Plasma Detachment and Heat Load ControlPoster
Research on fundamental plasma physics in the divertor region for DEMO divertor design has required divertor simulation experiments using linear devices. Existing linear devices are still unable to fully replicate DEMO-class divertor plasmas. To address this limitation, we have constructed a new linear device, the Pilot GAMMA PDX-SC (PGX-SC), designed to verify high-density plasma sources and...
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Ryuichi Sano (QST)22/05/2026, 09:50G. Power Exhaust, Plasma Detachment and Heat Load ControlPoster
Feedback control of radiative power from in divertor plasmas by D₂ fuel gas injection, through carbon radiation, is considered for the next operation phase of JT-60SA. The location of gas injection ports can affect the radiation response. For feedback control, the radiation profile must be converted into measurement signals, taking into account the diagnostic fields of view. In JT-60SA,...
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Mr Lloyd Baker (University of York)22/05/2026, 09:50G. Power Exhaust, Plasma Detachment and Heat Load ControlPoster
The STEP program run by UK Industrial Fusion Solutions Ltd aims to deliver a tritium self sufficient prototype fusion power plant generating 100 MW net electric power based on the spherical tokamak. The compact spherical geometry of STEP’s SPP-2 design raise significant exhaust challenges, with powers crossing the separatrix reaching Psep ≈ 110−140 MW, corresponding to Psep/R0 ≈ 25−32 MW/m. To...
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Dr Haosheng Wu (NEMO Group, Dipartimento Energia, Politecnico di Torino, Corso Duca degli Abruzzi 24, 10129 Torino, Italy.)22/05/2026, 09:50G. Power Exhaust, Plasma Detachment and Heat Load ControlPoster
The SOLPS-ITER is employed to model advanced divertor configurations in the SPARC tokamak aiming to explore potential solutions to the power exhaust challenge [1]. The configurations studied include the standard Single Null Divertor (SND), Super-X Divertor (SXD), and X-Point Target Divertor (XPTD).
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The outer targets of the SXD and XPTD configurations benefit from their advanced geometries,... -
Eric Emdee (Princeton Plasma Physics Laboratory)22/05/2026, 09:50G. Power Exhaust, Plasma Detachment and Heat Load ControlPoster
The lithium vapor cave is a detached divertor concept that uses a single Private Flux Region (PFR) baffle to confine a dense lithium vapor cloud, reducing target heat flux while minimizing contamination of the main plasma. Plasma flows are driven by deuterium puffing to control lithium transport from the divertor to the main plasma. Previous SOLPS-ITER modeling demonstrated sufficient outer...
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Matthias Bernert (IPP Garching)22/05/2026, 09:50G. Power Exhaust, Plasma Detachment and Heat Load ControlPoster
Power exhaust is a crucial issue for future fusion reactors and X-point radiation might provide a valuable solution. X-point radiators (XPR) are usually initialized by impurity seeding and are observed in almost all currently operating tokamaks. In JET they were first observed in 2016. In the recent JET campaigns, including the final DT campaign (DTE3), the XPR was investigated in...
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Kenneth Lee (Swiss Plasma Center, EPFL)22/05/2026, 09:50G. Power Exhaust, Plasma Detachment and Heat Load ControlPoster
Future tokamak reactors are expected to generate divertor heat fluxes that greatly exceed the technological limits of plasma-facing components if unmitigated. While a partially-detached conventional single-null (SN) divertor is currently foreseen for ITER, alternative divertor concepts based on strategic magnetic shaping and neutral baffling are under investigation to improve power exhaust...
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Margaret Porcelli (Princeton University)22/05/2026, 09:50G. Power Exhaust, Plasma Detachment and Heat Load ControlPoster
The lithium vapor cave is a detached divertor design that aims to mitigate divertor heat flux via near-target lithium evaporation with a private flux region (PFR) baffle to contain dense lithium vapor [1]. The future implementation of a lithium vapor cave in NSTX-U is planned to be a staged process where the early iterations consist of a single, unbaffled tile insert comprising a 15$^\circ$...
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Francesca Zarotti (ENEA)22/05/2026, 09:50G. Power Exhaust, Plasma Detachment and Heat Load ControlPoster
In the Divertor Tokamak Test (DTT) facility, the Limiter Inboard First Wall (LIFW) plays a key role in shielding the standard inboard wall modules from direct plasma contact during plasma-limited operation, such as ramp-up and ramp-down phases, negative triangularity configurations, transient events, and accidental scenarios. The limiter design relies on modules that protrude radially toward...
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Máté Szűcs (Max Planck Institute for Plasma Physics)22/05/2026, 09:50G. Power Exhaust, Plasma Detachment and Heat Load ControlPoster
The X-Point Radiator (XPR) regime is a promising exhaust solution for future large-size tokamaks, featuring a cold, dense, highly radiative region above the X-point, inside the confined region. Such regimes have been achieved experimentally on several tokamaks, with different seeded impurities, and ELM suppression is seen when the XPR reaches a threshold height [1]. Modeling with SOLPS-ITER...
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Mr Yu-Chih Liang (Max Planck Institute for Plasma Physics Garching)22/05/2026, 09:50G. Power Exhaust, Plasma Detachment and Heat Load ControlPoster
The power exhaust problem in the future large-scale fusion reactors necessitates operational regimes that can avoid extreme heat fluxes onto the plasma-facing components. One promising regime is the X-point radiator (XPR), which relies on a highly radiative, cold and dense plasma volume forming above the X-point, and which can be accessed via impurity seeding. Experimentally, the height of the...
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Morgan Shafer (ORNL)22/05/2026, 09:50G. Power Exhaust, Plasma Detachment and Heat Load ControlPoster
Experiments performed on DIII-D demonstrate that extending the outer divertor leg allows for expanding the volume for impurity and hydrogenic/fuel radiation as required for dissipation in detachment. This is roughly in line with convective transport estimates although deep detachment can trend toward the peak radiation moving to the X-point. Convective estimates relate the spatial scale for...
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Matteo Maria Robaldo (Politecnico di Torino)22/05/2026, 09:50G. Power Exhaust, Plasma Detachment and Heat Load ControlPoster
The next generation of fusion reactors will face unprecedented conditions in terms of power exhaust from the burning plasma. Quantifying heat loads due to impurity radiation following line and bremsstrahlung emission, as well as recombination, is essential for the thermo-mechanical design of plasma-facing components. This work describes the development of an integrated framework for the...
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Mate Karacsonyi (ITER Organization, CS 90 046, 13067 St Paul Lez Durance Cedex, France; HUN-REN Centre for Energy Research, Institute for Atomic Energy Research, Budapest, Hungary)22/05/2026, 09:50G. Power Exhaust, Plasma Detachment and Heat Load ControlPoster
Predicting different key boundary plasma constraints such as peak heat load to divertor targets and first wall, density at the separatrix and impurity influx as a function of the measurable control parameters (i.e. divertor neutral pressure, impurity seeding rate etc.) is crucial to prevent damage to the divertor targets and achieve required core plasma performance in fusion devices. In the...
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Stefan Dasbach (DIFFER)22/05/2026, 09:50G. Power Exhaust, Plasma Detachment and Heat Load ControlPoster
Understanding and controlling the detachment and power-exhaust behavior of SPARC is essential for ensuring divertor survivability in a device characterized by narrow scrape-off layers and high parallel heat fluxes.
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We apply SOLPS-NN, a neural network surrogate model trained on SPARC SOLPS-ITER simulations, to explore the SOL and divertor operational space for SPARC.
In this context, we... -
Dominik Brida (Max-Planck-Institute for Plasma Physics)22/05/2026, 09:50G. Power Exhaust, Plasma Detachment and Heat Load ControlPoster
Power exhaust remains a key challenge for steady-state operation of future tokamak reactors. More than 90% of the heating power must be dissipated through radiation before reaching the divertor targets to ensure sufficient material lifetime and low sputtering. At the same time, the divertor must enable efficient pumping of fuel and helium neutrals, and prevent impurity accumulation in the...
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Rebecca Masline (MIT Plasma Science and Fusion Center)22/05/2026, 09:50G. Power Exhaust, Plasma Detachment and Heat Load ControlPoster
Managing power and particle exhaust is a central challenge for a compact, high-field fusion pilot plant, where power-plant-level exhaust in a limited divertor volume leads to severe thermal and particle loading to the material surfaces. Achieving stable, dissipative divertor operation under these conditions (while simultaneously ensuring effective helium removal) requires divertor geometries,...
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Kevin Verhaegh (Eindhoven University of Technology)22/05/2026, 09:50G. Power Exhaust, Plasma Detachment and Heat Load ControlPoster
Fusion energy is accelerating through conventional (DEMO) and alternative compact reactor designs, that are potentially faster and cheaper to build (e.g., ARC, STEP). Power exhaust is a key challenge and a potential show-stopper for all these designs. Recent experiment show the key benefits of strongly shaped Alternative Divertor Configurations (ADCs) [1-5], demonstrating their potential as a...
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Dr Kevin Verhaegh (Department of Applied Physics and Science Education, Eindhoven University of Technology)22/05/2026, 09:50G. Power Exhaust, Plasma Detachment and Heat Load ControlPoster
Power exhaust remains a critical challenge for ITER, DEMO, and next-generation tokamaks, with unmitigated exhaust fluxes in an ITER-like device estimated at 100MWm−2, for which real-time control is essential. Maintaining detachment is further complicated in reactors by transients, caused by pellet fuelling and MHD perturbations (sawteeth, LH/HL transitions, unsuppressed ELMs, ...), resulting...
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Menglong Zhao (Lawrence Livermore National Laboratory)22/05/2026, 09:50G. Power Exhaust, Plasma Detachment and Heat Load ControlPoster
The Vacuum Neutral Model (VNM) has been implemented in UEDGE to account for neutral bypassing in the far scrape-off layer (SOL) [1], which lies outside the UEDGE computational mesh. In this work, the model is further extended to incorporate kinetic effects in the neutral flux leaking from the UEDGE boundary into the vacuum region. From a kinetic perspective, the dominant contribution to the...
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Hailong Du (GNOI)22/05/2026, 09:50G. Power Exhaust, Plasma Detachment and Heat Load ControlPoster
The divertor is one of the most crucial components of a tokamak device, serving two primary functions: heat exhaust and helium ash removal. In future fusion reactors, the parallel power flux entering the divertor is expected to exceed 1 GW/m². The divertor is expected to experience extremely high thermal loads in future fusion reactors. Therefore, the development of an advanced divertor is...
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Daniël Maris (DIFFER)22/05/2026, 09:50G. Power Exhaust, Plasma Detachment and Heat Load ControlPoster
Robust control of the heat and particle exhaust is required for machine protection in future high power magnetic confinement devices such as ITER. Understanding the dynamic behaviour of the plasma boundary is essential both for control design [1] and more generally to improve knowledge of the relevant transient physics. Recently, the inherently dynamic MHD code JOREK [2] has been extended with...
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Tom Looby (Commonwealth Fusion Systems)22/05/2026, 09:50G. Power Exhaust, Plasma Detachment and Heat Load ControlPoster
Commonwealth Fusion Systems (CFS) is rapidly assembling the SPARC tokamak, with commissioning of many systems already underway. SPARC is a high field (12T), high current (8.7MA) device capable of achieving an energy gain of 11 when operating in H-mode with DT fuel. While the high magnetic field enables high fusion performance, it also results in a narrow heat flux width (between 0.3-0.6mm)...
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Christian Avanzato (University of Tuscia)22/05/2026, 09:50G. Power Exhaust, Plasma Detachment and Heat Load ControlPoster
TRUST (Tuscia Research University Small Tokamak) is a new university-scale tokamak currently under design at the University of Tuscia (UNITUS).The main parameters are as follows [1,2]:R= 0.32 m, a= 0.11 m, A= 2.80, K≈ 1.7, Ip≈ 0.11 MA, Bt≈ 0.77 T, H98≈ 0.8, βpol(1)≈0.11, li(3)≈0.77 and will be operated with an ohmic power of Pohm = 0.3 MW.
TRUST is scheduled to be deployed in three phases,...
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Ivo Classen (DIFFER)22/05/2026, 09:50I. Plasma Edge and First Wall DiagnosticsPoster
Divertor detachment is the leading candidate for solving the heat exhaust problem in future fusion reactors. Key to understanding detachment is the interaction of the plasma with a background of neutral particles in the divertor region. Collisions of the plasma with these neutral background particles result in a rich range of physical and chemical processes, causing the plasma to dissipate its...
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Dr Laurent Marot (University of Basel, Department of Physics)22/05/2026, 09:50I. Plasma Edge and First Wall DiagnosticsPoster
The metallic First Mirrors (FMs) will play a crucial role in most optical diagnostic systems in ITER. As the initial elements in the optical path of diagnostic systems, the FMs will be subjected to deposition of the first tungsten wall materials and to regular boronization, compromising their optical properties. The FMs would thus need periodic cleaning to restore their optical properties,...
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Dr Gennady Sergienko (FZJ)22/05/2026, 09:50I. Plasma Edge and First Wall DiagnosticsPoster
A compact laser-induced breakdown spectroscopy (LIBS) set-up recently operated on a remote handling arm in the JET tokamak after end of operation in a radioactive environment. The picosecond-LIBS set-up has successfully measured the fuel retention and surface composition on different plasma-facing components in-situ at 840 positions [1]. This LIBS set-up uses a spectroscopic plasma...
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Jun Ren (University of Tennessee - Knoxville)22/05/2026, 09:50I. Plasma Edge and First Wall DiagnosticsPoster
Quantification of shine-through (not absorbed by the plasma) heat flux from neutral beam injection (NBI) is essential for protecting plasma-facing components (PFCs). In this work, we present the direct measurement of heat flux deposition from NBI shine through on the DIII-D first wall using newly implemented, high temperature capable Surface Eroding Thermocouple (SETC) sensors [1]. The SETCs...
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Jari Likonen (VTT Technical Research Centre of Finland)22/05/2026, 09:50I. Plasma Edge and First Wall DiagnosticsPoster
The feasibility of laser-induced breakdown spectroscopy (LIBS) for measuring fuel retention was first demonstrated in 2024 in a tokamak operating with tritium. This was achieved using a remotely controlled in-situ application at JET [1]. Following the third deuterium-tritium campaign, DTE3, and the in-situ LIBS experiment selected plasma-facing components were removed from the JET vacuum...
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K. E. Ramachandran (Comenius University, Faculty of Mathematics, Physics and Informatics, Bratislava, Slovakia)22/05/2026, 09:50I. Plasma Edge and First Wall DiagnosticsPoster
Boron layers are widely employed in magnetic-confinement fusion devices due to their strong oxygen gettering capability and their role in reducing impurity release from plasma-facing components. Accurate characterization of boron film thickness, erosion behaviour using laser ablation, and fuel retention is essential for predictive plasma–wall interaction modelling in ITER- relevant...
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Adam McLean (LLNL)22/05/2026, 09:50I. Plasma Edge and First Wall DiagnosticsPoster
A multiband interpretation of infrared emission allows for accounting of spatial and temporal variations in emissivity for metallic armor materials and thus accurate determination of surface temperature and heat flux in a fusion device. Without adequately accounting for true emissivity of material in the imaged scene, the situation where true surface emissivity is less than expected can lead...
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Alex Klasing (University of Wisconsin, Madison)22/05/2026, 09:50I. Plasma Edge and First Wall DiagnosticsPoster
The Helically Symmetric eXperiment (HSX) is a medium sized stellarator optimized to study confinement properties in a quasi-helically symmetric (QHS) configuration. The QHS configuration of HSX exhibits non-resonant divertor like behavior in its edge region [1]. In addition, HSX is equipped with a set of auxiliary coils leading to a wide range of possible magnetic configurations allowing for...
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Peeter Paris (UT)22/05/2026, 09:50I. Plasma Edge and First Wall DiagnosticsPoster
Laser-induced breakdown spectroscopy (LIBS) is a technique developed for determining fuel retention in ITER plasma-facing components (PFCs) [1]. It can also analyse the formation of various layers on PFCs caused by material redeposition eroded from other regions. A series of experiments was conducted at the JET tokamak after the third deuterium-tritium campaign, DTE3, to demonstrate the...
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Christine Stollberg (EPFL)22/05/2026, 09:50I. Plasma Edge and First Wall DiagnosticsPoster
Accurate spectroscopic diagnostics for tokamak and stellarator divertors rely on collisional–radiative models (CRMs), whose predictive power is often limited by uncertain collisional rates [1]. The Resonant Antenna Ion Device (RAID) at the Swiss Plasma Center provides a controlled, steady-state plasma environment relevant to magnetic confinement fusion that is ideally suited for validating...
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Dr Dongcheol Seo (Korea Institute of Fusion Energy)22/05/2026, 09:50I. Plasma Edge and First Wall DiagnosticsPoster
During the 2023 KSTAR experimental campaign, the lower divertor was replaced with tungsten monoblock plasma-facing components. The transition from carbon to tungsten is expected to substantially modify impurity sources and transport in the divertor plasma. However, prior to this upgrade, KSTAR lacked a dedicated diagnostic for measuring D-alpha emission in the divertor region, limiting...
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Sanath Shetty (FMPI, Comenius University, Bratislava)22/05/2026, 09:50I. Plasma Edge and First Wall DiagnosticsPoster
Transition metal borides (TMBs) are a class of compounds known for their exceptional mechanical strength, thermal stability, and chemical inertness. These compounds, formed by strong covalent bonding between transition metals and boron, are widely studied for applications in cutting tools, coatings, and high-temperature environments such as thermal fusion reactors and aerospace components [1]....
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Lauren Nuckols (Oak Ridge National Lab)22/05/2026, 09:50I. Plasma Edge and First Wall DiagnosticsPoster
A reciprocating, actively water-cooled probe is currently under development to be deployed in the WEST tokamak for long pulse/high fluence plasma-material interaction (PMI) and materials transport studies. The WEST long-pulse probe (LPP) probe head will be composed of tungsten coated onto an additively manufactured advanced Cu alloy, GRCop-42, body. GRCop-42 was selected as the primary...
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Alysée Khan (EPFL-SPC)22/05/2026, 09:50I. Plasma Edge and First Wall DiagnosticsPoster
Controlling heat and particle fluxes on plasma-facing components remains a major challenge on the path toward ITER and future fusion reactors. These fluxes are strongly influenced by the dynamics in the boundary region, where turbulence and plasma flows partly determine first-wall heat and particle loads, as well as impurity transport, ultimately affecting sputtering and core plasma...
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C. Christopher Klepper (Oak Ridge National Laboratory, Oak Ridge, TN 37831-6169, United States of America)22/05/2026, 09:50I. Plasma Edge and First Wall DiagnosticsPoster
There is renewed interest in using the sub-divertor for diagnosis of the fusion plasma burn process, as this region of the reactor chamber would not require access via the main chamber wall and T-breeding blanket [1]. In the referenced study, it was shown that it would be feasible to control the DT burn by feedback from $^3$He concentration measurement in the sub-divertor, assuming the...
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Trenton Brewer (Tokamak Energy Ltd.)22/05/2026, 09:50I. Plasma Edge and First Wall DiagnosticsPoster
In previous ST40 experimental campaigns, distinct wide and narrow scrape-off layer (SOL) profile widths have been observed [Zhang et al., Nuclear Materials and Energy 41 (2024)]. The “wide” profiles follow traditional scalings built on a multi-device empirical database [T. Eich et al., 2013 Nucl. Fusion 53 093031], while the “narrow” profiles have been found to be an order of magnitude...
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Dr Kyu-Dong Lee (Korea Institute of Fusion Energy)22/05/2026, 09:50I. Plasma Edge and First Wall DiagnosticsPoster
Maintaining plasma performance stability and enhancing equipment durability during the long-term KSTAR experimental campaign is crucial. To achieve these goals, removing contaminants attached to the inner wall of the tokamak device is essential. Among various wall cleaning methods, Glow Discharge Cleaning (GDC) is one of the most effective techniques. At KSTAR, GDC is typically conducted...
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Seungmin Bong (KAIST)22/05/2026, 09:50I. Plasma Edge and First Wall DiagnosticsPoster
A suite of Langmuir probes (LPs) installed on the KSTAR lower tungsten divertor, consisting of 52 in the D-port and another 52 in the L-port, has been operated since 2023. The D-port Langmuir probes are battery-biased at -240 V to measure temporal behavior of the ion saturation currents. During the 2024 campaign, a single sweeping Langmuir probe driven by a bipolar supply (-100 to +100 V, 1...
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