A microwave imaging reflectometer (MIR) instrument, capable of simultaneously measuring the poloidal and radial structure of density fluctuations, has been developed for the DIII-D tokamak and installed in May 2013. The two-dimensional capabilities of MIR are made possible with 12 vertically separated sightlines and four-frequency operation (corresponding to four radial channels). The 48-channel DIII-D MIR system has a tunable source that can be stepped in 500 μs increments over a range of 56 to 74 GHz. Its multi-channel, multi-frequency capabilities and high sensitivity permit visualization and quantitative diagnosis of density perturbations, including correlation length, wavenumber, mode propagation velocity, and dispersion.
Fig 1: Typical DIII-D MIR parameters, source: https://fusion.gat.com/pubs-ext/NuclFus/A27746abs.pdf, credit to C. M.Muscatello
The DIII-D MIR concept has undergone numerous technological and system-level upgrades both in optics and electronics since earlier microwave imaging systems, thereby permitting a higher level of robustness and flexibility:
The MIR system on DIII-D shares the same 270 degree midplane port with the ECEI system (Fig 2), allowing for simultaneous measurements for both temperature and density fluctuations of the same plasma volume. Numerous exciting physics results, like ELM (Fig 3) , EHO (Fig 4-6) related studies , Alfven Eigenmodes (Fig 7) etc., have been obtained from it.
Fig 2: Schematic of co-located ECEI/MIR system
Fig 4: Spectrogram of EHO from MIR data
Fig 3: Images of electron density and temperature fluctuations inside the DIII-D tokamak fusion plasma. The top two plots are spectra of representative channels from (a) MIR and (b) ECEI showing fluctuations in the interval between edge-localized mode activity. The bottom two plots are (c) density and (d) temperature image reconstructions of the 66-kHz fluctuation at 1860 ms and each panel is separated by 1.9 μs (source: IEEE Transactions on Plasma Science 42 (10), 2734-2735)
Fig 5: Frequency versus wavenumber spectrogram from MIR shows clearly the EHO and broadband MHD have opposite sign in phase velocity, partially implies they are drove from different mechanism.
Fig 6: Measured and synthetic MIR power spectra in poloidal wave numbers with frequencies (a) 57 GHz and (b) 58 GHz for an n = 1 EHO in DIII-D shot #157102, at 2420 ms
Fig 7: a) A single-channel spectrogram from MIR reveals a number of reversed-shear-induced Alfvén eigenmodes that sweep between 40 and 120 kHz as the safety factor, q, is varied during the Lmode phase of DIII-D discharge 161127. b) At 450 ms, both RSAEs and TAEs are observed by the diagnostic. Fitting a line through the spectrum of TAE modes provides an estimate of the Doppler shift and natural TAE frequency, i.e. the observed frequency in the absence of rotation. c) As qmin decreases, RSAEs sweep upward toward the TAE band. d) At the upper limit of their sweep, RSAEs couple to modes in the TAE gap.
Fig 5: Phased arrays for beam shaping and steering, and their application in fusion plasma diagnostics
Fig 6: Block diagram of the electronically controlled phase shifter transmitter system