Explanipedia

Overview of fuel retention and recovery in JET deuterium–tritium operation Open

A. Widdowson, S. Brezinsek, T. Dittmar, D. Douai, R. Felton , et al. · 2025

Tritium inventory build-up is a safety and economic issue for next step fusion devices and power plants. JET with a beryllium wall and tungsten divertor brings a unique contribution on fuel retention and recovery in a metallic device, as i…

Scrape-off layer and divertor physics: Chapter 5 of the special issue: on the path to tokamak burning plasma operation Open

K. Krieger, S. Brezinsek, J.W. Coenen, H. Frerichs, A. Kallenbach , et al. · 2025

Since the publication of the review Progress in the ITER Physics Basis (PIPB) in 2007, significant progress has been made in understanding the processes at the plasma-material interface. This review, part of the ITPA Nuclear Fusion Special…

Characterization of detachment inferred from the Balmer line ratios in JET-ILW low-confinement mode plasmas Open

Vesa‐Pekka Rikala, M. Groth, A. Meigs, D. Reiter, B. Lomanowski , et al. · 2025

Spectroscopic measurements of the hydrogenic Balmer-α and Balmer-γ line emission in JET-ILW low-confinement mode (L-mode) deuterium plasmas are used to assess the onset of volume recombination in the low-field side (LFS) divertor. The evol…

Investigation of H-mode density limit in mixed protium–deuterium plasmas at JET with ITER-like wall Open

A. Huber, G. Sergienko, M. Groth, D. Keeling, M. Wischmeier , et al. · 2024

Analysis of comparable discharges fuelled by either deuterium or protium reveals a clear relationship between the isotope mass and the H-mode density limit. Notably, the density limit is significantly lower in protium, showing a reduction …

Wall conditions in WEST during operations with a new ITER grade, actively cooled divertor Open

A. Gallo, P. Moreau, D. Douai, Tomás Alarcón, K. Afonin , et al. · 2024

Future fusion reactors like ITER and DEMO will have all-tungsten (W) walls and long pulses. These features will make wall conditioning more difficult than in most of the existing devices. The W Environment Steady-state Tokamak (WEST) is on…

Hydrogen isotopic ratio by residual gas analysis during the JET DT campaigns Open

G. Gervasini, L. Laguardia, D. Douai, D. Matveev, D. Borodin , et al. · 2024

The analysis of hydrogen isotope content is crucial for understanding the operation of fusion devices. Hydrogen isotopic analysis in the core and plasma edge is conducted through neutron and spectroscopic diagnostics. In the case of exhaus…

Helium plasma operations on ASDEX Upgrade and JET in support of the non-nuclear phases of ITER Open

A. Hakola, M. Balden, M. Baruzzo, R. Bisson, S. Brezinsek , et al. · 2024

For its initial operational phase, ITER has until recently considered using non-nuclear hydrogen (H) or helium (He) plasmas to keep nuclear activation at low levels. To this end, the Tokamak Exploitation Task Force of the EUROfusion Consor…

Isotope effects and Alfvén eigenmode stability in JET H, D, T, DT, and He plasmas Open

R. A. Tinguely, P. Puglia, S. Dowson, M. Porkoláb, D. Douai , et al. · 2024

While much about Alfvén eigenmode (AE) stability has been explored in previous and current tokamaks, open questions remain for future burning plasma experiments, especially regarding exact stability threshold conditions and related isotope…

Modeling of plasma facing component erosion, impurity migration, dust transport and melting processes at JET-ILW Open

I. Borodkina, D. Borodin, D. Douai, J. Romazanov, E. Pawelec , et al. · 2024

An overview of the modeling approaches, validation methods and recent main results of analysis and modeling activities related to the plasma-surface interaction (PSI) in JET-ILW experiments, including the recent H/D/T campaigns, is present…

ICRH-related impurity source and control across experiments in H, D, T plasmas at JET-ILW Open

A. Chomiczewska, W. Gromelski, I. Ivanova‐Stanik, E. Kowalska-Strzęciwilk, N. Wendler , et al. · 2024

The experimental and theoretical analysis were focused on experiments conducted to assess the effect of plasma isotopes, protium (H), deuterium (D), and tritium (T) on ion cyclotron resonance heating (ICRH) related plasma wall interactions…

Isotope effects and Alfven eigenmode stability in JET H, D, T, DT, and He plasmas Open

R. A. Tinguely, P. Puglia, S. Dowson, M. Porkolab, D. Douai , et al. · 2024

While much about Alfven eigenmode (AE) stability has been explored in previous and current tokamaks, open questions remain for future burning plasma experiments, especially regarding exact stability threshold conditions and related isotope…

Changeover between helium and hydrogen fueled plasmas in JET and WEST Open

T. Wauters, R. Bisson, E. Delabie, D. Douai, A. Gallo , et al. · 2024

International audience

Tritium removal from JET-ILW after T and D–T experimental campaigns Open

D. Matveev, D. Douai, T. Wauters, A. Widdowson, I. Jepu , et al. · 2023

After the second Deuterium–Tritium Campaign (DTE2) in the JET tokamak with the ITER-Like Wall (ILW) and full tritium campaigns that preceded and followed after the DTE2, a sequence of fuel recovery methods was applied to promote tritium re…

The JET hybrid scenario in Deuterium, Tritium and Deuterium-Tritium Open

J. Hobirk, C. Challis, A. Kappatou, E. Lerche, D. Keeling , et al. · 2023

The JET hybrid scenario has been developed from low plasma current carbon wall discharges to the record-breaking Deuterium-Tritium plasmas obtained in 2021 with the ITER-like Be/W wall. The development started in pure Deuterium with refine…

Tritium neutral beam injection on JET: calibration and plasma measurements of stored energy Open

D. King, R. Sharma, C. Challis, A. Bleasdale, E. Delabie , et al. · 2023

Neutral beam injection (NBI) is a flexible auxiliary heating method for tokamak plasmas, capable of being efficiently coupled to the various plasma configurations required in the Tritium and mixed deuterium-tritium experimental campaign on…

Comparison of ion cyclotron wall conditioning discharges in hydrogen and helium in JET Open

Yu.V. Kovtun, T. Wauters, D. Matveev, R. Bisson, I. Jepu , et al. · 2023

This paper explores the plasma parameters of helium and hydrogen Ion Cyclotron Wall Conditioning (ICWC) discharges performed in JET as part of a He/H fuelling changeover experiment. The conducted study shows that plasma with a higher densi…

Evidence of Electron Heating by Alpha Particles in JET Deuterium-Tritium Plasmas Open

V. Kiptily, R. Dümont, M. Fitzgerald, D. Keeling, S. E. Sharapov , et al. · 2023

The fusion-born alpha particle heating in magnetically confined fusion machines is a high priority subject for studies. The self-heating of thermonuclear fusion plasma by alpha particles was observed in recent deuterium-tritium (D-T) exper…

The role of isotope mass and transport for H-mode access in tritium containing plasmas at JET with ITER-like wall Open

G. Birkenmeier, E.R. Solano, I.S. Carvalho, J. C. Hillesheim, E. Delabie , et al. · 2023

The required heating power, , to access the high confinement regime (H-mode) in tritium containing plasmas is investigated in JET with ITER-like wall at a toroidal magnetic field of T and a plasma current of MA. …

ICRH operations and experiments during the JET-ILW tritium and DTE2 campaigns Open

Philippe Jacquet, E. Lerche, M. Mantsinen, D. Van Eester, K. Kirov , et al. · 2023

2021 has culminated with the completion of the JET-ILW DTE2 experimental campaign. This contribution summarizes Ion Cyclotron Resonance Heating (ICRH) operations from system and physics point of view. Improvements to the (ICRH) system, to …

Characterisation of divertor detachment onset in JET-ILW hydrogen, deuterium, tritium and deuterium–tritium low-confinement mode plasmas Open

M. Groth, В. В. Солоха, S. Aleiferis, S. Brezinsek, M. Brix , et al. · 2022

Measurements of the ion currents to and plasma conditions at the low-field side (LFS) divertor target plate in low-confinement mode plasmas in the JET ITER-like wall materials configuration show that the core plasma density required to det…

Developments and Challenges in the Design of the ITER DRGA Open

C. C. Klepper, Ephrem Delabie, I. Jepu, P. Andrew, T. M. Biewer , et al. · 2022

We report the ITER Diagnostic Residual Gas Analyzer (DRGA) will measure the distribution of gas species, i.e., deuterium (D), tritium (T), and impurities, in the divertor exhaust stream and in the plasma periphery, with time resolution rel…

The broadening of SOL profiles in JET tritium plasma and its impact on machine operation Open

H.J. Sun, S. Silburn, I.S. Carvalho, D. King, C. Giroud , et al. · 2022

Unusually high power loads on the beryllium limiter caused by neutral beam re-ionisation, and much cooler divertor target surfaces were observed during the recent JET tokamak tritium campaign. As both phenomena are driven by scrape-off lay…

Determination of best operation parameters of electron cyclotron wall conditioning in KSTAR Open

T. Nakano, D. Douai, S. Vartanian, M. Fukumoto, S.H. Son , et al. · 2022

Dependence of EC injection power (0.6 and 1.4 MW), EC injection width (0.1–1.0 s) and prefilled He pressure (2.8×10−5∼2.2×10−3 mbar) on D2 outgas efficiency is investigated at a toroidal field of 2.4 T in a poloidal trapped particle config…

The power threshold of H-mode access in mixed hydrogen–tritium and pure tritium plasmas at JET with ITER-like wall Open

G. Birkenmeier, E.R. Solano, E. Lerche, D. Taylor, D. Gallart , et al. · 2022

The heating power to access the high confinement mode (H-mode), P LH , scales approximately inversely with the isotope mass of the main ion plasma species as found in (protonic) hydrogen, deuterium and tritium plasmas in many fusion facili…

Overview of the TCV tokamak experimental programme Open

H. Reimerdes, M. Agostini, E. Alessi, S. Alberti, Y. Andrèbe , et al. · 2022

The tokamak à configuration variable (TCV) continues to leverage its unique shaping capabilities, flexible heating systems and modern control system to address critical issues in preparation for ITER and a fusion power plant. For the 2019–…

Isotope removal experiment in JET-ILW in view of T-removal after the 2nd DT campaign at JET Open

T. Wauters, D. Matveev, D. Douai, J. Banks, R. Buckingham , et al. · 2022

A sequence of fuel recovery methods was tested in JET, equipped with the ITER-like beryllium main chamber wall and tungsten divertor, to reduce the plasma deuterium concentration to less than 1% in preparation for operation with tritium. T…

Evaluation of tritium retention in plasma facing components during JET tritium operations Open

A. Widdowson, J.P. Coad, Y. Zayachuk, I. Jepu, E. Alves , et al. · 2021

An assessment of the tritium (T) inventory in plasma facing components (PFC) during JET T and deuterium-tritium (DT) operations is presented based on the most comprehensive ex situ fuel retention data set on JET PFCs from the 2015-2016 ILW…

Investigation of plasma wall interactions between tungsten plasma facing components and helium plasmas in the WEST tokamak Open

E. Tsitrone, B. Pégouriè, J. Gunn, E. Bernard, V. Bruno , et al. · 2021

ITER will operate with a tungsten divertor, a material featuring surface morphology changes when exposed to helium plasmas, in particular the formation of the so called tungsten fuzz under specific conditions. Investigating interactions be…

Understanding tungsten erosion during inter/intra-ELM periods in He-dominated JET-ILW plasmas Open

A. Huber, S. Brezinsek, V. Huber, E.R. Solano, G. Sergienko , et al. · 2021

Tungsten erosion was quantified during inter/intra-ELM periods in He-dominated JET-ILW plasmas by optical emission spectroscopy. The intra-ELM tungsten sputtering in helium plasmas, which dominates the total W source, prevails by a factor …

Cherenkov probes and runaway electrons diagnostics Open

R. Kwiatkowski, M. Rabiński, Marek J. Sadowski, J. Żebrowski, P. Karpinski , et al. · 2021

D. Douai YOU? Author Swipe