NbTi superconductors with low ac loss: A review

MN Wilson - Cryogenics, 2008 - Elsevier
Niobium titanium is still the superconductor of choice for magnets where the field changes
rapidly with time. To keep the hysteretic ac losses within bounds, it must be finely …

Initial physics achievements of large helical device experiments

O Motojima, H Yamada, A Komori, N Ohyabu… - Physics of …, 1999 - pubs.aip.org
The Large Helical Device (LHD) experiments [O. Motojima, et al., Proceedings, 16th
Conference on Fusion Energy, Montreal, 1996 (International Atomic Energy Agency, Vienna …

Far infrared laser interferometer system on the Large Helical Device

K Kawahata, K Tanaka, Y Ito, A Ejiri… - Review of scientific …, 1999 - pubs.aip.org
A multichannel far-infrared laser interferometer system has been developed for the
measurement of the spatial and temporal behaviors of the electron density on the Large …

Development of pellet injector system for large helical device

H Yamada, R Sakamoto, Y Oda, T Hiramatsu… - Fusion engineering and …, 2000 - Elsevier
A multi-pellet injector system has been developed as a fundamental fueling tool for the
Large Helical Device (LHD). Since a primary goal of the LHD project is demonstration of …

Impact of pellet injection on extension of the operational region in LHD

R Sakamoto, H Yamada, K Tanaka, K Narihara… - Nuclear …, 2001 - iopscience.iop.org
Pellet injection has been used as a primary fuelling scheme in the Large Helical Device.
With pellet injection, the operational region of NBI plasmas has been extended to higher …

Overview of LHD experiments

M Fujiwara, K Kawahata, N Ohyabu, O Kaneko… - Nuclear …, 2001 - iopscience.iop.org
During the first two years of the LHD experiment the following results have been achieved:(i)
higher T e (T e (0)= 4.4 keV at⟨ ne⟩= 5.3× 10 18 m-3 and P abs= 1.8 MW);(ii) higher …

Needed computations and computational capabilities for stellarators

AH Boozer - Physics of Plasmas, 2024 - pubs.aip.org
Stellarator plasmas are externally controlled to a degree unparalleled by any other fusion
concept, magnetic or inertial. This control is largely through the magnetic fields produced by …

Liquid stub tuner for ion cyclotron heating

R Kumazawa, T Mutoh, T Seki, F Sinpo… - Review of scientific …, 1999 - pubs.aip.org
Ion cyclotron range of frequency (ICRF) heating on the large helical device (LHD) is
characterized by high power (up to 12 MW) and steady state operation (30 min). The LHD is …

Conceptual design of a subcritical research reactor for inertial fusion energy with the J-EPoCH facility

A Iwamoto, R Kodama - High Energy Density Physics, 2020 - Elsevier
Abstract The Japan Establishment for a Power-laser Community Harvest (J-EPoCH) is
proposed as a next generation laser facility having multi-purpose high repetition laser …

Plasma startup by neutral beam injection in the large Helical Device

O Kaneko, Y Takeiri, K Tsumori, Y Oka… - Nuclear …, 1999 - iopscience.iop.org
Plasma was successfully built up by neutral beams alone in LHD. After injecting 1.6 MW
neutral beams through a low density neutral gas target of 10-3 Pa for about 0.3 s, fully …