Abstract
The mission of the National Centralized Tokamak (NCT) is to establish high-beta steady-state plasma operation for DEMO and to contribute to ITER. Plasma performance with high-beta conditions is discussed. It is found that near break-even class plasma (QDTeq≥0.7) with high beta (βN ≥ 3.5) is achievable with 25 MW of NB power at IP = 4.0 MA and an aspect ratio of 2.6. High beta with steady-state full current drive is possible with 13 MW of NB power at IP = 1.5-1.7 MA. In the engineering design activity of NCT, the strength of the support structure and strength of material for the conductor is confirmed for the superconducting coils, and the successful progress of R&D of boron-loaded resin for neutron shielding is discussed.
Original language | English |
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Pages (from-to) | 1599-1605 |
Number of pages | 7 |
Journal | Fusion Engineering and Design |
Volume | 81 |
Issue number | 8-14 PART B |
DOIs | |
Publication status | Published - Feb 2006 |
Event | Proceedings of the Seventh International Symposium on Fusion Nuclear Technology ISFNT-7 Part B - Duration: May 22 2005 → May 27 2005 |
All Science Journal Classification (ASJC) codes
- Civil and Structural Engineering
- Nuclear Energy and Engineering
- General Materials Science
- Mechanical Engineering