Explanipedia

High-resolution visible spectroscopy for ion temperature and flow velocity measurements of the TCV divertor plasma Open

Richard Ducker, H. Reimerdes, A. Perek · 2025

A high-resolution spectroscopic system was installed on the Tokamak à Configuration Variable (TCV), whose toroidal lines-of-sight (LOS) cross the divertor region. This system simultaneously measures the Doppler broadening and Doppler shift…

A novel understanding of the role of plasma-molecular kinetics on divertor power exhaust Open

N. Osborne, K. Verhaegh, D. Moulton, Stefan Mijin, H. Reimerdes , et al. · 2025

During detachment, a buffer of neutral atoms and molecules builds up between the target and the ionising plasma. Collisions between the plasma and the molecules play an important role in the detachment process. Studies of plasma-molecular …

Verification of techniques for accelerated and stable SOLPS-ITER simulations including plasma drifts Open

M. Carpita, E. Tonello, C. Colandrea, O. Février, H. Reimerdes , et al. · 2025

SOLPS-ITER is a widely employed transport code for Scrape-Off Layer (SOL) modeling, commonly used to assist experimental interpretation in current tokamak experiments, and for the design of future devices. An aspect of particular importanc…

Demonstration of Super-X divertor exhaust control for transient heat load management in compact fusion reactors Open

B. Kool, K. Verhaegh, Gijs Derks, T. Wijkamp, J.T.W. Koenders , et al. · 2025

Nuclear fusion could offer clean, abundant energy. However, managing the power exhausted from the core fusion plasma towards the reactor wall remains a major challenge. This is compounded in emerging compact reactor designs promising more …

MHD, disruptions and control physics: Chapter 4 of the special issue: on the path to tokamak burning plasma operation Open

I. Bandyopadhyay, V. Igochine, O. Sauter, S.A. Sabbagh, Jong-Kyu Park , et al. · 2025

In this chapter, we review the progress in MHD stability, disruptions and control in magnetic fusion research that has occurred over the past (more than) one and a half decades since the publication by Hender et al in 2007 on the same topi…

Separatrix ion to electron temperature ratio in the TCV and ASDEX Upgrade tokamaks Open

M. Cavedon, D. Brida, F. Bagnato, Reinart Coosemans, H. Reimerdes , et al. · 2025

Increased focus has been recently given to the ion temperature T i near the separatrix and in the scrape-off layer (SOL) due to its impact on plasma confinement, wall sputtering, heat fluxes, and edge turbulence. In current tokamaks, high …

Experimental characterization of inter-ELM modes in type-I ELMy scenarios at TCV using the thermal helium beam diagnostic Open

M. La Matina, M. Agostini, M. Ugoletti, Y.S. Wang, C. Theiler , et al. · 2025

The high confinement regime (H-mode) is considered fundamental for high-performance operation in next-step tokamaks. It is generally characterized by the occurrence of edge localized modes (ELMs), even though several no-ELM and small-ELM r…

Neutral pressure measurement in TCV tokamak using ASDEX-type pressure gauges Open

H. Reimerdes, H. Elaian, M. Baquero-Ruiz, Byron W. Brown, M. Gospodarczyk , et al. · 2025

Probing the neutral gas distribution at the edge of magnetic confinement fusion devices is critical for plasma exhaust studies. In the TCV tokamak, a set of ASDEX-type hot ionization pressure gauges (APGs) has been installed for fast, in s…

Divertor shaping with neutral baffling as a solution to the tokamak power exhaust challenge Open

K. Verhaegh, J. Harrison, D. Moulton, B. Lipschultz, N. Lonigro , et al. · 2025

Exhausting power from the hot fusion core to the plasma-facing components is one fusion energy's biggest challenges. The MAST Upgrade tokamak uniquely integrates strong containment of neutrals within the exhaust area (divertor) with extrem…

Interpretation of divertor ion temperature measurements from an attached towards a detached regime Open

L. Martinelli, D. Mykytchuk, B.P. Duval, P. Blanchard, M. Carpita , et al. · 2025

We present simultaneous profiles of the poloidal distribution of electron temperature and density ( T e , n e ), the poloidal emissivity distributions of a range of spectral lines together with the corresponding ion temperatures, T i , in …

X-point radiation: From discovery to potential application in a future reactor Open

M. Bernert, T.O.S.J. Bosman, T. Lunt, O. Pan, B. Sieglin , et al. · 2025

Power exhaust is a crucial issue for future fusion reactors. Divertor detachment and the required power dissipation fractions of about 95% are foreseen to be achieved by impurity seeding. In a tokamak, at high seeding levels the radiation …

Overview of the third JET deuterium-tritium campaign Open

A. Kappatou, M. Baruzzo, A. Hakola, E. Joffrin, D. Keeling , et al. · 2025

JET returned to deuterium-tritium operations in 2023 (DTE3 campaign), approximately two years after DTE2. DTE3 was designed as an extension of JET’s 2022-2023 deuterium campaigns, which focused on developing scenarios for ITER and DEMO, in…

An upper pressure limit for low-<i>Z</i> benign termination of runaway electron beams in TCV Open

M. Hoppe, J. Decker, U. Sheikh, S. Coda, C. Colandrea , et al. · 2025

We present a model for the particle balance in the post-disruption runaway electron plateau phase of a tokamak discharge. The model is constructed with the help of, and applied to, experimental data from TCV discharges investigating the so…

Investigating the influence of divertor baffles on nitrogen-seeded detachment in TCV with SOLPS-ITER simulations and TCV experiments Open

Guangyu Sun, H. Reimerdes, C. Theiler, B.P. Duval, M. Carpita , et al. · 2025

Plasma edge simulations with the SOLPS-ITER code are performed to study the influence of divertor baffles on nitrogen-seeded detachment in Tokamak à Configuration Variable (TCV) single-null, L-mode discharges. Scans of nitrogen seeding rat…

X-point radiator control and its dynamics in ASDEX Upgrade and JET deuterium–tritium discharges Open

T.O.S.J. Bosman, M. Bernert, Lennard Ceelen, B. Sieglin, J.T.W. Koenders , et al. · 2024

Control of heat exhaust is essential for the operation of power producing fusion reactors. Here, we present results of heat exhaust feedback control experiments in JET and AUG. In JET, we demonstrate the first X-point radiator (XPR) contro…

Access to an ELM-suppressed X-point radiator regime in TCV snowflake minus configurations Open

H. Reimerdes, C. Theiler, M. Bernert, B.P. Duval, O. Février , et al. · 2024

TCV’s operating regime with an X-point radiator (XPR) has been broadened by changing the magnetic geometry. XPRs have properties that could make them an attractive power exhaust solution for fusion reactors. These include the conversion of…

A novel understanding of the role of plasma-molecular kinetics on divertor power exhaust Open

Nicholas J. Osborne, K. Verhaegh, D. Moulton, H. Reimerdes, P. Ryan , et al. · 2024

During detachment, a buffer of neutral atoms and molecules builds up between the target and the ionising plasma. Collisions between the plasma and the molecules play an important role in the detachment process. Studies of plasma-molecular …

Validating reduced models for detachment onset and reattachment times on MAST-U Open

S. Henderson, M. Bernert, D. Brida, Gijs Derks, S. Elmore , et al. · 2024

Two reduced models for predicting detachment onset and divertor reattachment times are validated on MAST Upgrade (MAST-U). These models are essential for future tokamak reactor design, providing rapid calculations based primarily on engine…

Edge plasma turbulence simulations in detached regimes with the SOLEDGE3X code Open

V. Quadri, P. Tamain, Y. Marandet, H. Bufferand, N. Rivals , et al. · 2024

Neutral pressure measurement in TCV tokamak using ASDEX-type pressure gauges Open

Guotong Sun, H. Reimerdes, H. Elaian, M. Baquero-Ruiz, M. Gospodarczyk , et al. · 2024

Probing the neutral gas distribution at the edge of magnetic confinement fusion devices is critical for plasma exhaust studies. In the TCV tokamak, a set of ASDEX-type hot ionization pressure gauges (APGs) has been installed for fast, in-s…

First demonstration of Super-X divertor exhaust control for transient heat load management in compact fusion reactors Open

B. Kool, K. Verhaegh, Gijs Derks, T. Wijkamp, J.T.W. Koenders , et al. · 2024

Nuclear fusion could offer clean, abundant energy. However, managing the power exhausted from the core fusion plasma towards the reactor wall remains a major challenge, compounded in emerging compact reactor designs promising more cost-eff…

Experiments and SOLEDGE3X modeling of dissipative divertor and X-point Radiator regimes in WEST Open

N. Rivals, N. Fedorczak, P. Tamain, H. Bufferand, G. Ciraolo , et al. · 2024

X-Point Radiator (XPR) regimes have been obtained in WEST tokamak experiments with nitrogen seeding during the experimental campaigns of 2023 and 2024. These experiments showed the formation of a stable toroidal radiating ring near the X-p…

First demonstration of Super-X divertor exhaust control for transient heat load management in compact fusion reactors Open

B. Kool, K. Verhaegh, Gianne Derks, T. Wijkamp, N. Lonigro , et al. · 2024

Nuclear fusion could offer clean, abundant energy. However, managing the immense power exhausted from the core fusion plasma towards the divertor remains a major challenge. This is compounded in emerging compact reactor designs which promi…

X-point radiator and power exhaust control in configurations with multiple X-points in TCV Open

S. Gorno, O. Février, C. Theiler, Timo Ewalds, F. Felici , et al. · 2024

Novel power exhaust solutions are being developed to address the challenge of integrating a high performance fusion core plasma with a well-protected divertor, if the single null configuration does not scale to a reactor device. This work …

Modelling of power exhaust in TCV positive and negative triangularity L-mode plasmas Open

E. Tonello, F. Mombelli, O. Février, G. Alberti, T Bolzonella , et al. · 2024

L-mode negative triangularity (NT) operation is a promising alternative to the positive triangularity (PT) H-mode as a high-confinement edge localised mode-free operational regime. In this work, two TCV Ohmic L-mode core density ramps with…

Comparison of detachment in Ohmic plasmas with positive and negative triangularity Open

O. Février, C.K. Tsui, G. Durr-Legoupil-Nicoud, C. Theiler, M. Carpita , et al. · 2024

In recent years, negative triangularity (NT) has emerged as a potential high-confinement L-mode reactor solution. In this work, detachment is investigated using core density ramps in lower single null Ohmic L-mode plasmas across a wide ran…

Comparison of reduced model predictions for divertor detachment onset and reattachment timescales in ASDEX Upgrade and JET experiments Open

S. Henderson, M. Bernert, D. Brida, M. Cavedon, P. David , et al. · 2024

Building on prior analysis of ASDEX Upgrade (AUG) experiments (Henderson et al 2023 Nucl. Fusion 63 086024), this study compares simple analytical formula predictions for divertor detachment onset and reattachment timescales in JET experim…

Validation of SOLPS-ITER simulations against the TCV-X21 reference case Open

Y.S. Wang, C. Colandrea, D.S. Oliveira, C. Theiler, H. Reimerdes , et al. · 2024

This paper presents a quantitative validation of Scrape-Off Layer Plasma Simulation-ITER (SOLPS-ITER) simulations against the TCV-X21 reference case and provides insights into the neutral dynamics and ionization source distribution in this…

Multi-machine benchmark of the self-consistent 1D scrape-off layer model DIV1D from stagnation point to target with SOLPS-ITER Open

Gijs Derks, E. Westerhof, M. van Berkel, J H Jenneskens, J.T.W. Koenders , et al. · 2024

This paper extends a 1D dynamic physics-based model of the scrape-off layer (SOL) plasma, DIV1D, to include the core SOL and possibly a second target. The extended model is benchmarked on 1D mapped SOLPS-ITER simulations to find input sett…

Parallel flows as a key component to interpret Super-X divertor experiments Open

M. Carpita, O. Février, H. Reimerdes, C. Theiler, B.P. Duval , et al. · 2024

The Super-X Divertor (SXD) is an alternative divertor configuration leveraging total flux expansion at the Outer Strike Point (OSP). While the extended 2-Point Model (2PM) predicts facilitated detachment access and control in the SXD confi…

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