| Title of Device | Large Helical Device (LHD) |
|---|---|
| Organization | National Institute for Fusion Science (Japan) |
| Location | Toki, Japan |
| A. Device concept and components | |
| Concept | Heliotron |
| Vacuum vessel: -- Plasma facing material: | Stainless steel (SUS316) [1] |
| Divertor/limiter facing material | - |
| Working Gas | H, He [1] |
| Boundary configuration: | Built-in double-null divertor [1] |
| Toroidal magnetic field (on axis), B (T): | 3 [3] |
| Remarks | Employment of superconducting coils |
| B. Plasma geometry | |
| Major radius, R(m): | 3.9 [1] |
| Minor radius, a(m): | 0.65 [1] |
| Plasma volume (m3): | 30 |
| Remarks: | - |
| C. Plasma parameters (maximum values) | |
| Central ion temperature, Ti (keV): | 5 [3] |
| Central electron temperature, Te (keV): | 10 [3,4] |
| Line averaged plasma density, <n> (1020 m-3): | 1.6 [3] |
| Central electron density, n (1020 m-3): | - |
| Plasma current, I (MA): | 0 [1] |
| Discharge pulse duration (s): | 127 [3] |
| Plasma beta, <β> (%): | 3.2 [3] |
| Stored energy, (MJ): | 1.16 [3] |
| Energy confinement time, τE (s): | 0.36 [3] |
| Remarks: | - |
| D. Plasma heating and current drive (device values) | |
| Ohmic heating, (MW): | - |
| NBI heating, (MW): | 9 [3] |
| RF heating: -IC: (MW): | 2.7 [3] |
| RF heating: -EC: (MW): | 1.9 [3] |
| RF heating: -LH: (MW): | 0 |
| E. Reactor relevant plasma performance parameters | |
| Triple fusion product, ( 1020 keV s m-3): | 2.2E19 [3] |
| QDT factor (if available): | NA |
| F. Input information | |
| Date of entry | 13-Dec-2002 |
| Data was entered by: | H. Yamada |
Reference: