| Title of Device | TPE-RX, Toroidal Pinch experiment - RX [1] |
|---|---|
| Organization | National Institute of Advanced Undustrial Science and Technology |
| Location | 1-1-1 Umezono, Tsukuba, Ibaraki 305-8568, Japan |
| A. Device concept and components | |
| Concept | RFP |
| Vacuum vessel: -- Plasma facing material: | Stainless steel (SUS316L) [1] |
| Divertor/limiter facing material | Molybdenum fixed limiters [1] |
| Working Gas | Duterium |
| Boundary configuration: | Limiter |
| Toroidal magnetic field (on axis), B (T): | |
| Remarks | Normal conducting |
| B. Plasma geometry | |
| Major radius, R(m): | 1.72 [1] |
| Minor radius, a(m): | 0.45 [1] |
| Plasma volume (m3): | 6.9 |
| Remarks: | Circular cross-section |
| C. Plasma parameters (maximum values) | |
| Central ion temperature, Ti (keV): | 0.5 [2][3] |
| Central electron temperature, Te (keV): | 1 [2][3] |
| Line averaged plasma density, <n> (1020 m-3): | 0.4 [2][4] |
| Central electron density, n (1020 m-3): | 0.5 [2][4] |
| Plasma current, I (MA): | 0.5 achieved, 1.0 designed maximum [1][2] |
| Discharge pulse duration (s): | 0.1 [1] |
| Plasma beta, <β> (%): | 15% poloidal beta [2][3] |
| Stored energy, (MJ): | 0.006 [2][3] |
| Energy confinement time, τE (s): | 0.004 [2][3] |
| Remarks: | 2,6-8: improved confinement mode, 3,4: gas puffing |
| D. Plasma heating and current drive (device values) | |
| Ohmic heating, (MW): | 15 [2] |
| NBI heating, (MW): | 1.9 [4] |
| RF heating: -IC: (MW): | nil |
| RF heating: -EC: (MW): | 0.01 |
| RF heating: -LH: (MW): | nil |
| E. Reactor relevant plasma performance parameters | |
| Triple fusion product, ( 1020 keV s m-3): | 10-4-10-3 |
| QDT factor (if available): | - |
| F. Input information | |
| Date of entry | 7-May-2003 |
| Data was entered by: | Y.Yagi |
Reference: