Physics basis for the first ITER tungsten divertor

RA Pitts, X Bonnin, F Escourbiac, H Frerichs… - Nuclear Materials and …, 2019‏ - Elsevier
On the eve of component procurement, this paper discusses the present physics basis for
the first ITER tungsten (W) divertor, beginning with a reminder of the key elements defining …

A high-density and high-confinement tokamak plasma regime for fusion energy

S Ding, AM Garofalo, HQ Wang, DB Weisberg, ZY Li… - Nature, 2024‏ - nature.com
The tokamak approach, utilizing a toroidal magnetic field configuration to confine a hot
plasma, is one of the most promising designs for develo** reactors that can exploit …

Highest fusion performance without harmful edge energy bursts in tokamak

SK Kim, R Shousha, SM Yang, Q Hu, SH Hahn… - Nature …, 2024‏ - nature.com
The path of tokamak fusion and International thermonuclear experimental reactor (ITER) is
maintaining high-performance plasma to produce sufficient fusion power. This effort is …

Progress in the development and understanding of a high poloidal-beta tokamak operating scenario for an attractive fusion pilot plant

S Ding, AM Garofalo - Reviews of Modern Plasma Physics, 2022‏ - Springer
The high poloidal-beta (β P) regime was first proposed as a high bootstrap current scenario
for a steady-state fusion pilot plant (FPP) in the 1990s (Kikuchi in Nucl Fusion 30: 265 …

Overview of the SPARC physics basis towards the exploration of burning-plasma regimes in high-field, compact tokamaks

P Rodriguez-Fernandez, AJ Creely… - Nuclear …, 2022‏ - iopscience.iop.org
The SPARC tokamak project, currently in engineering design, aims to achieve breakeven
and burning plasma conditions in a compact device, thanks to new developments in high …

The JOREK non-linear extended MHD code and applications to large-scale instabilities and their control in magnetically confined fusion plasmas

M Hoelzl, GTA Huijsmans, SJP Pamela… - Nuclear …, 2021‏ - iopscience.iop.org
JOREK is a massively parallel fully implicit non-linear extended magneto-hydrodynamic
(MHD) code for realistic tokamak X-point plasmas. It has become a widely used versatile …

Prospects of core–edge integrated no-ELM and small-ELM scenarios for future fusion devices

E Viezzer, ME Austin, M Bernert, KH Burrell… - Nuclear Materials and …, 2023‏ - Elsevier
One of our grand challenges towards fusion energy is the achievement of a high-
performance plasma core coupled to a boundary solution. The high confinement mode (H …

Overview of initial negative triangularity plasma studies on the ASDEX Upgrade tokamak

T Happel, T Pütterich, D Told, M Dunne… - Nuclear …, 2022‏ - iopscience.iop.org
An overview of results of negative triangularity (NT) studies from the ASDEX Upgrade
tokamak (AUG) is given. Moderate values of the triangularity in the range of δ average≈ …

Analysis and expansion of the quasi-continuous exhaust (QCE) regime in ASDEX Upgrade

M Faitsch, T Eich, GF Harrer, E Wolfrum, D Brida… - Nuclear …, 2023‏ - iopscience.iop.org
The quasi-continuous exhaust (QCE) regime, formerly known as either type-II ELM or small
ELM regime is studied in ASDEX Upgrade. The regime is a natural type-I ELM-free H-mode …

Divertor heat flux challenge and mitigation in SPARC

AQ Kuang, S Ballinger, D Brunner, J Canik… - Journal of Plasma …, 2020‏ - cambridge.org
Owing to its high magnetic field, high power, and compact size, the SPARC experiment will
operate with divertor conditions at or above those expected in reactor-class tokamaks …