| Title of Device | TRIAM-1M |
|---|---|
| Organization | Advanced Fusion Research Center, Research Institute for Applied Mechanics, Kyushu University (Japan) |
| Location | Kasuga, Japan |
| A. Device concept and components | |
| Concept | Tokamak |
| Vacuum vessel: -- Plasma facing material: | Stainless Steel (SUS304L) [3] |
| Divertor/limiter facing material | Molybdenum [3] |
| Working Gas | H [1] |
| Boundary configuration: | Single null configuration or Limiter configuration [3] |
| Toroidal magnetic field (on axis), B (T): | 8 [1] |
| Remarks | Employment of superconducting coils |
| B. Plasma geometry | |
| Major radius, R(m): | 0.8 [1] |
| Minor radius, a(m): | 0.12 x 0.18 [1] |
| Plasma volume (m3): | 0.23 (limiter configuration) [3] |
| Remarks: | - |
| C. Plasma parameters (maximum values) | |
| Central ion temperature, Ti (keV): | 5 *S[3] |
| Central electron temperature, Te (keV): | 1.5 [2] |
| Line averaged plasma density, <n> (1020 m-3): | 0.7 [1] |
| Central electron density, n (1020 m-3): | - |
| Plasma current, I (MA): | 0.5 [1] |
| Discharge pulse duration (s): | 11406 [6] |
| Plasma beta, <β> (%): | 0.07 [4] |
| Stored energy, (MJ): | ~2 [4] |
| Energy confinement time, τE (s): | 0.01 [4] |
| Remarks: | - |
| D. Plasma heating and current drive (device values) | |
| Ohmic heating, (MW): | - |
| NBI heating, (MW): | 0 |
| RF heating: -IC: (MW): | 0 |
| RF heating: -EC: (MW): | 0.2 [5] |
| RF heating: -LH: (MW): | 0.45 [3][4] |
| E. Reactor relevant plasma performance parameters | |
| Triple fusion product, ( 1020 keV s m-3): | 0.0022 [4] |
| QDT factor (if available): | NA |
| F. Input information | |
| Date of entry | 17-Jan-2003 |
| Data was entered by: | M. Sakamoto |
Reference: