sballin
JET, currently operating in the UK, is the tokamak closest to producing more fusion power than absorbed heating power. It would be a nice surprise if it achieved this in its upcoming research program using deuterium-tritium fuel. But to reliably pass this milestone and get closer to producing electricity, we need to build tokamaks bigger, like ITER, or with a stronger magnetic field, like SPARC. Neither one will produce electricity, but they will allow us to study the potentially different plasma environment and materials issues at high fusion power.
Electricity-producing tokamaks are in the extremely early conceptual design phase (DEMO, ARC) and will require much more research on tritium breeding and materials that can withstand insane levels of heating and irradiation.
HL-2M specs (paywalled): https://doi.org/10.1016/j.fusengdes.2015.06.106
The default search looks for folder names too, so searching "[folder name]" will bring up all the notes in that folder, and "[folder name] [note name]" will bring up the specific note in that folder, as of the latest commit a few minutes ago :)
At the moment I'm analyzing data from W7-X in Germany. It's a really cool device off the beaten path of tokamaks but seriously catching up in performance [1].
[1] See fig. 15 of https://iopscience.iop.org/article/10.1088/1361-6587/aaec25
[1] https://w3.pppl.gov/~szweben/Papers/coauthorpapers/DarrowRSI...
By the way, the unusual shapes of the coils can be understood intuitively from this picture: https://imgur.com/a/Bq3ABfQ. A plasma needs to be confined with a magnetic field in order to be heated to extreme temperatures, and a toroidal field (produced by the currents in the red coils) is unstable due to particle orbit drifts. You need to add a twist to the field for it to be stable (using the green coils). But if you unroll the surface of the torus, you can approximate the currents in both green and red coils using the discrete blue coils, and they're easier to build.
[1] https://aip.scitation.org/doi/abs/10.1063/1.860481 [2] http://iopscience.iop.org/article/10.1088/0029-5515/27/5/018...
Most imaging in fusion is done like this because of space constraints, magnetic fields, and neutron fluxes.
Our camera looks through a pinhole in the vessel wall, but it sits a few meters away from the machine and gets that view through a bundle of optical fibers. There wouldn't be enough space to place the camera right at the pinhole because of the magnets and their cooling systems, and the magnetic fields would be pretty high. The camera needs to be shielded from the fields for its electronics to work properly, and the shielding box perturbs the magnets' field, so moving the camera far away is a good idea. We don't worry about neutrons, because W7-X plasmas are fueled with stable helium and hydrogen (no deuterium or tritium so far, mainly due to onerous nuclear regulations in Germany), and these fuels don't produce many neutrons at all.
I do research at W7-X, so I can confirm that to the best of my knowledge, the design was computed a long time ago. Building the actual device took a while.