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Vera Oberhauser (UKAEA)07/10/2026, 14:00Mean-field codesLightning talk + poster
Magnetic flux expansion in the scrape-off layer (SOL) is a critical mechanism for spreading exhaust heat loads across divertor target surfaces, and its accurate modelling is essential for predicting performance in present and next-generation devices. This phenomenon is typically modelled using fluid codes, which incorporate flux expansion geometrically through area factors in the governing...
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Mr Tom Ashton-Key (Imperial College London)07/10/2026, 14:04Turbulence codesLightning talk + poster
Hermes-3 is a multi-component plasma fluid code based on the BOUT++ framework [1] which simulates turbulence in the edge region and scrape-off-layer of tokamak plasmas with full 3D diverted tokamak geometry. The effect of turbulent magnetic fluctuations due to local turbulent currents has been implemented in Hermes-3, including ‘magnetic flutter’, how local magnetic fluctuations impact the...
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John Lloyd Baker (University of York, UKAEA)07/10/2026, 14:08Mean-field codesLightning talk + poster
\noindent The STEP program run by UK Fusion Energy Ltd (UKFE, UKAEA group) aims to deliver a tritium self sufficient prototype fusion power plant generating 100 MW net electric power based on the spherical tokamak concept. The compact spherical geometry of STEP's SPP-2 design raises significant exhaust challenges, with powers crossing the separatrix reaching $P_\text{sep} \approx110 -...
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Sid Leigh (UKAEA)07/10/2026, 14:12Mean-field codesLightning talk + poster
We present the benchmarking of one-dimensional (1D) simulations comparing a newly developed 1D exhaust code RMK_REX [1] with the modelling suite SOLPS-ITER [2]. RMK_REX is developed in the ReMKiT1D framework [3] for fluid-kinetic and collisional-radiative modelling, with the aim of simulating detached plasmas with non-local electron effects. The benchmark serves to calibrate RMK_REX to...
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Owen Parry (UKAEA)07/10/2026, 14:16Mean-field codesLightning talk + poster
Molecules are expected to play a critical role in the physics of detachment in tokamak divertors.
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Fluid modelling of molecular species has been a longstanding and conspicuous absentee from the Hermes-3 feature list, but recent changes to the code have greatly simplified its implementation.
The handling of chemical reactions has been substantially overhauled, introducing a framework that... -
Sebastian Ruiz Gonzalez (University of York)07/10/2026, 14:20Research Software EngineeringLightning talk + poster
The divertor problem is one of the biggest ongoing challenges in the fusion energy sector. The magnetic geometry and topology of the divertor region in tokamaks significantly influences plasma edge dynamics as well as heat and particle exhaust.[1] Advanced divertor configurations, like the snowflake (SF) divertor, offer advantages in mitigating heat loads and enhancing plasma performance.[2]...
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Lin Shih (University of York)07/10/2026, 14:24Mean-field codesLightning talk + poster
Understanding the mechanism of edge transport in magnetic confinement fusion devices is critical for future reactors, as it determines how effectively high heat loads can be exhausted to achieve the sustainability of the devices.
In this work, the multi-fidelity exhaust code Hermes-3 [1] is employed to model scrape-off layer (SOL) transport using a fluid framework, solving the Braginskii...
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Alessandro Geraldini (University of York)07/10/2026, 14:28Turbulence codesLightning talk + poster
When using a fluid model to simulate the plasma in the Scrape-Off Layer, boundary conditions are imposed at the entrance of the boundary layer next to the solid targets, where the model assumptions fail. This boundary layer reflects most electrons away from the target. With finite ion temperature, the largest length scale in the boundary layer is the collisional mean free path (along the...
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Mantas Abazorius (United Kingdom Atomic Energy Authority)07/10/2026, 14:32Mean-field codesLightning talk + poster
In magnetic confinement fusion devices, the divertor is often negatively charged because electrons are more mobile and are preferentially captured by the divertor. This negative charge is shielded by a positively charged Debye sheath. In magnetised plasmas, another layer of width of the order of the ion gyroradius, known as the magnetic presheath, forms on top of the Debye sheath. In this...
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David Moulton (UKAEA)08/10/2026, 14:00Kinetic neutralsLightning talk + poster
We present transient simulations of the MAST-U tokamak using the SOLPS-ITER model, operated in time-dependent mode and including time-dependent kinetic neutrals. Given the expected audience, we focus on the numerical requirements and challenges to run SOLPS-ITER in time-dependent mode, as well as the separate validation of the Eirene and B2.5 codes.
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Steven Thomas (MIT PSFC)08/10/2026, 14:04Mean-field codesLightning talk + poster
Steven Thomas1,*, Jerry W. Hughes1, Alex Tookey2, Davis Easley3, Yacopo Damizia4,
Bart Lomanowski3, Saskia Mordijck4, Ekin Öztürk4, Scott Silburn2,
and the MAST Upgrade Team2,†1MIT Plasma Science and Fusion Center, Cambridge, MA 02139, USA
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2UKAEA, Culham Campus, Abingdon, Oxfordshire, OX14 3DB, UK
3Oak Ridge National Laboratory, Oak Ridge, TN 37831-6169, USA
4William & Mary,... -
Naomi Carey (UKAEA)08/10/2026, 14:08Research Software EngineeringLightning talk + poster
Surrogate enable the rapid evaluation of plasma quantities across different divertor operating conditions. Building on previous work on surrogate modelling for geometry, fuelling and impurity seeding studies, this work focuses on the continued development and evaluation of deep learning-based surrogates trained to predict 2D plasma variables from simulation inputs (both 1d and 2D).
We...
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Niall Bootland (STFC)08/10/2026, 14:12Research Software EngineeringLightning talk + poster
Hermes-3 uses the pressure-diffusion model to represent the cross-field transport of fluid neutrals. This enables neutral advection, conduction and viscosity in the perpendicular direction according to diffusion coefficients which are each subject to flux limitation.
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Hermes-3 has a fully implicit solver. Due to the inherent nonlinearity in the neutral equations and high neutral speeds through... -
Annika Stier (IPP-Greifswald)08/10/2026, 14:16Mean-field codesLightning talk + poster
As part of the effort to establish Hermes-3 as a simulation tool for the stellarator edge and scrape-off layer, we examine the current implementation of the advanced fluid neutral model.
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Due to the toroidal asymmetry of the strike line, stellarator scenarios could be more sensitive to artificial anisotropies in the neutral transport than tokamaks. We therefore evaluate the neutral anisotropy... -
Nassim Maaziz (IPP-Greifswald)08/10/2026, 14:20Mean-field codesLightning talk + poster
The island divertor concept was proposed for power and particle exhaust in low-shear stellarators, such as Wendelstein 7-X. So far low downstream density has been experimentally measured. Stronger scaling of the downstream density is necessary to ensure the reactor-relevance of the island divertor in terms of particle exhaust. Numerical studies of the island divertor SOL require 3D codes,...
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Chris MacMackin (UK Atomic Energy Authority)08/10/2026, 14:24Research Software EngineeringLightning talk + poster
Hermes-3 is a multifluid plasma simulation code, built on BOUT++. It is used for simulating transport and turbulence at the edge of magneticically-confined plasmas. It uses a system of modular components which make it highly flexible. I have provide research software engineering skills to support the ongoing development and optimisation of Hermes-3 and BOUT++. I will be presenting the work I...
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David Bold (IPP Greifswald)08/10/2026, 14:28Turbulence codesLightning talk + poster
In order to model the scrape-off layer of a fusion device,
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traditionally field aligned codes have been used. For stellarators, this is not feasible, and the flux coordinate independent approach (FCI) is used.
Aligning the grid with the boundary is challenging, and generating
body fitted, structured grids restricts the homogeneity and
orthogonality of the grid, making numerical integration... -
Amit Kharwandikar (Max-Planck-Institut für Plasmaphysik, Greifswald)08/10/2026, 14:32Mean-field codesLightning talk + poster
The development of a viable plasma exhaust solution is one of the principal challenges on the path towards stellarator fusion reactors. While the island divertor of Wendelstein 7-X (W7-X) has demonstrated excellent performance in terms of detachment and steady-state operation, its present open geometry limits neutral compression and particle exhaust. A closed divertor configuration is...
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