[HTML][HTML] Challenges towards an acceleration in stellarator reactors engineering: The dual coolant lithium–lead breeding blanket helical-axis advanced stellarator case

I Palermo, J Alguacil, JP Catalán… - Energy, 2024 - Elsevier
Under the ambitious EUROfusion mission of “bringing the stellarator line to technological
maturity”, the development of a Dual Coolant Lithium–Lead (DCLL) Breeding Blanket (BB) …

Design and development of high-temperature superconducting magnet system with joint-winding for the helical fusion reactor

N Yanagi, S Ito, Y Terazaki, Y Seino… - Nuclear …, 2015 - iopscience.iop.org
An innovative winding method is developed by connecting high-temperature
superconducting (HTS) conductors to enable efficient construction of a magnet system for …

High performance of neutral beam injectors for extension of LHD operational regime

Y Takeiri, O Kaneko, K Tsumori… - Fusion Science and …, 2010 - Taylor & Francis
High-power negative and positive ion-based neutral beam injectors (NBIs) are operated with
high reliability in the Large Helical Device (LHD). The total injection power is> 20 MW, and …

Development and application of real-time magnetic coordinate mapping system in the Large Helical Device

C Suzuki, K Ida, Y Suzuki, M Yoshida… - Plasma Physics and …, 2012 - iopscience.iop.org
We have newly developed a large-scale equilibrium database for real-time magnetic
coordinate mapping system in the Large Helical Device. Thousands of free-boundary …

Detachment stabilization with n/m= 1/1 resonant magnetic perturbation field applied to the stochastic magnetic boundary of the Large Helical Device

M Kobayashi, S Masuzaki, I Yamada, N Tamura… - Physics of …, 2010 - pubs.aip.org
It is found that the remnant island structure created by n/m= 1/1 resonant magnetic
perturbation field in the stochastic magnetic boundary of the Large Helical Device (LHD)[A …

Overview of results from the Large Helical Device

H Yamada - Nuclear Fusion, 2011 - iopscience.iop.org
The physical understanding of net-current-free helical plasmas has progressed in the Large
Helical Device (LHD) since the last Fusion Energy Conference in Geneva, 2008. The …

Characteristics of MHD equilibrium and related issues on LHD

KY Watanabe, Y Suzuki, S Sakakibara… - Fusion Science and …, 2010 - Taylor & Francis
In the vacuum of the Large Helical Device (LHD), we can change the plasma volume, the
aspect ratio, the ellipticity, the rotational transform, and the height of the magnetic hill …

Progress in the conceptual design of the helical fusion reactor FFHR-d1

N Yanagi, T Goto, J Miyazawa, H Tamura… - Journal of Fusion …, 2019 - Springer
The LHD-type helical fusion reactor FFHR has been studied to realize steady-state fusion
power generation without a need for current drive and free from disruption. The conceptual …

Anisotropic pressure effects on plasma equilibrium in toroidal systems

VD Pustovitov - Plasma Physics and Controlled Fusion, 2010 - iopscience.iop.org
General properties of anisotropic plasma equilibrium in tokamaks and stellarators are
considered within the approach allowing explicit analytical evaluation of the equilibrium …

Review of stellarator/heliotron design issues towards MFE DEMO

A Sagara, Y Igitkhanov, F Najmabadi - Fusion engineering and design, 2010 - Elsevier
The first review is presented for the recent stellarator designs of FFHR, HSR, ARIES-CS,
which are based on the experimental device projects of LHD, W-7X, NCSX, respectively …