Published 2000 | Version v1
Book

Progress in LHD experiment

  • 1. National Institute for Fusion Science, Toki, Gifu (Japan)

Description

In the third campaign (07.13.99-12.14.99), NBI (≤4.2 MW), ICRH (≤1.4 MW) and ECRH (≤0.9 MW) were used to heat the plasma in LHD. The carbon tiles were installed as divertor plates, resulting in significant reduction in metal impurity concentration (Fe). The maximum field used in the experiment is 2.9 T. Upgrading of the key hardware systems led to (i) higher Te [Te(0)=4.4 keV at n-bare=5.3 x 1018 m-3 and Pabc=1.8 MW], (ii) higher confinement [τE=0.3 s, Te(0)=1.1 keV at ne(0)=6.5 x 1019 m-3 and Pabc=2.0 MW], (iii) higher stored energy Wp=880 kJ, (iv) higher volume averaged β-bar=2.4% (at B=1.3T). The temperature pedestal enhances the confinement significantly (50% higher than the ISS95 scaling). The ICRH heating was found to be as efficient as NBI heating. Long pulse discharges (80 sec NBI shot, 68 sec ICRH shot) have been achieved without any technical difficulty. (author)

Part of:
Physics and technology for steady state plasmas

Additional details

Publishing Information

Publisher
Japan Society of Plasma Science and Nuclear Fusion Research
Imprint Place
Nagoya (Japan)
ISBN
4-9900586-5-8
Imprint Title
Physics and technology for steady state plasmas
Imprint Pagination
628 p.
Journal Page Range
p. 3-9

Conference

Title
10. international Toki conference on plasma and controlled nuclear fusion
Acronym
ITC-10
Dates
18-22 Jan 2000
Place
Toki, Gifu (Japan)

Optional Information

Notes
9 refs., 11figs., 1 tab. Imprint:Published in Journal of Plasma and Fusion Research SERIES, Volume 3