CFETR: Difference between revisions
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== Machine configuration == | == Machine configuration == | ||
CFETR is designed as a superconducting [[tokamak|tokamak]]. | |||
{| class="wikitable" align="center" border="1" | {| class="wikitable" align="center" border="1" | ||
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|Minor radius, a (m) || 1.6 | |Minor radius, a (m) || 1.6 | ||
|- | |- | ||
|Toroidal field | |Toroidal field, B<sub>T</sub> (T) || 4.5 - 5 | ||
|- | |- | ||
|Plasma current, I<sub>p</sub> (MA) || 8 - 10 | |Plasma current, I<sub>p</sub> (MA) || 8 - 10 | ||
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== References == | == References == | ||
[http://fire.pppl.gov/FPA14_Chinese_CFETR_Wan.pdf The Magnetic Fusion Program in China - Roadmap and Progress, December 2014] | [http://fire.pppl.gov/FPA14_Chinese_CFETR_Wan.pdf The Magnetic Fusion Program in China - Roadmap and Progress, December 2014] | ||
[[Category:Toroidal confinement devices]] | |||
Latest revision as of 08:17, 1 October 2018
CFETR is China's approach to an experimental fusion test reactor facility. The China Fusion Engineering Test Reactor (CFETR) will be of similar size to ITER and is envisaged to start construction in 2020 and operation in 2030.
Machine configuration
CFETR is designed as a superconducting tokamak.
| Parameter | Value |
|---|---|
| Major radius, R0 (m) | 5.7 |
| Minor radius, a (m) | 1.6 |
| Toroidal field, BT (T) | 4.5 - 5 |
| Plasma current, Ip (MA) | 8 - 10 |
| Edge safety factor, q95 | 3 |
| Normalised beta, βN | 2.0 |
References
The Magnetic Fusion Program in China - Roadmap and Progress, December 2014