[HTML][HTML] Recent progress of plasma exhaust concepts and divertor designs for tokamak DEMO reactors

N Asakura, K Hoshino, S Kakudate, F Subba… - Nuclear Materials and …, 2023 - Elsevier
The power exhaust concept and an appropriate divertor design are common critical issues
for tokamak DEMO design activities which have been carried out in Europe, Japan, China …

Integrated RMP-based ELM-crash-control process for plasma performance enhancement during ELM crash suppression in KSTAR

M Kim, G Shin, J Lee, WH Ko, H Han, SH Hahn… - Nuclear …, 2023 - iopscience.iop.org
Abstract The integrated Resonant Magnetic Perturbation (RMP)-based Edge-Localized
Mode (ELM)-crash-control process aims to enhance the plasma performance during the …

The advanced tokamak path to a compact net electric fusion pilot plant

RJ Buttery, JM Park, JT McClenaghan… - Nuclear …, 2021 - iopscience.iop.org
Physics-based simulations project a compact net electric fusion pilot plant with a nuclear
testing mission is possible at modest scale based on the advanced tokamak concept, and …

Development of compact tokamak fusion reactor use cases to inform future transport studies

C Holland, EM Bass, DM Orlov… - Journal of Plasma …, 2023 - cambridge.org
The OMFIT STEP (Meneghini et al., Nucl. Fusion, vol. 10, 2020, p. 1088) workflow has been
used to develop inductive and steady-state H-mode core plasma scenario use cases for a …

Overview of recent progress in 3D field physics in KSTAR

G Park, Y In, JK Park, WH Ko, J Lee, M Kim… - Journal of the Korean …, 2022 - Springer
Various 3D field physics challenges of magnetically confined plasmas arise when the
driving source comes from either externally applied non-axisymmetric 3D magnetic …

Progress in engineering design of CFETR toroidal field superconducting magnet

J Zheng, Y Song, F Liu, X Liu, K Lu, L Zhu, W Xu… - Fusion Engineering and …, 2022 - Elsevier
Abstract China Fusion Engineering Test Reactor (CFETR) is a national scientific research
project which is aimed to initially build fusion energy production up to 2× 1 0 8 W and to …

Progress in the conceptual design of the CFETR toroidal field coil with rectangular conductors

X Liu, F Wu, Z Wang, G Li, X Liu, H Li, J Li, Y Ren… - Nuclear …, 2020 - iopscience.iop.org
A comprehensive research facility project was approved in December 2018 with funding of
345 million EUR, to support the research and development of the China Fusion Engineering …

Validation of theory-based integrated modeling and new insights for a high-performance steady-state scenario with only RF heating on EAST

XM Zhai, JL Chen, N **ang, XZ Gong, J Huang… - Nuclear …, 2022 - iopscience.iop.org
Abstract Theory-based integrated modeling is validated against high-performance steady-
state core plasmas on EAST in the high poloidal beta (β p) regime with only RF heating …

Core-Pedestal Plasma Configurations in Advanced Tokamaks

E Hassan, CE Kessel, JM Park, WR Elwasif… - Fusion Science and …, 2023 - Taylor & Francis
Several configurations for the core and pedestal plasma are examined for a predefined
tokamak design by implementing multiple heating/current drive (H/CD) sources to achieve …

Thermal, electromagnetic and structural performance evaluation of CFETR toroidal field superconducting magnet

J Zheng, F Liu, X Liu, M Li, L Zhu, W Xu… - 2023 IEEE 6th …, 2023 - ieeexplore.ieee.org
As a critical component of Chinese Fusion Engineering Testing Reactor (CFETR), the
structural performance of TF magnet is very important. This paper mainly analyzes the …