Preliminary design of the COMPASS upgrade tokamak

Vondráček, P.; Pánek, R.; Hron, M.; Havlíček, J.; Weinzettl, V.; Todd, T.N.; Tskhakaya, D. D.; Cunningham, G.; Hacek, P.; Hromádka, Jakub; Junek, P.; Krbec, J.; Patel, Nisarg; Šesták, D.; Varju, J.; Adámek, Jiřı́; Balazsova, M.; Balner, V.; Barton, P.; Bielecki, J.; Bílková, P.; Błocki, J.; Bocian, D.; Bogár, K.; Bogar, O.; Boocz, P.; Borodkina, I.; Brooks, A.; Böhm, P.; Burant, J.; Casolari, A.; Cavalier, J.; Chappuis, P.; Dejarnac, R.; Dimitrova, M.; Dudak, M.; Ďuran, I.; Ellis, R.; Entler, Slavomír; Fang, Jiarong; Farník, M.; Ficker, O.; Fridrich, David; Fukova, S.; Gerardin, J.; Hanák, I.; Havránek, A.; Herrmann, A.; Horáček, J.; Hronova, O.; Imríšek, M.; Isernia, N.; Jaulmes, F.; Jerab, M.; Kindl, Vladimir; Komm, M.; Kovařík, K.; Kral, M.; Kripner, L.; Macúšová, E.; Majer, T.; Markovič, T.; Matveeva, E.; Mikszuta-Michalik, Katarzyna; Mohelnik, M.; Mysiura, I.; Naydenkova, D.; Nemec, I.; Ortwein, Rafal; Patočka, Karel; Peterka, M.; Podolník, A.; Procházka, Filip; Prevratil, Jan; Reboun, Jan; Scalera, Valentino; Scholz, M.; Svoboda, Jakub; Świerblewski, Jacek; Šos, M.; Tadros, M.; Titus, P.; Tomeš, M.; Torres, A.; Tracz, Grzegorz; Turjanica, Pavel; Varavin, M.; Veselovsky, V.; Villone, F.; Wąchal, Przemysław; Yanovskiy, Vadim; Zadvitskiy, G.; Zaja̧c, J.; Zak, A. R.; Zaloga, D.; Zelda, Jan; Zhang, H.

doi:10.1016/j.fusengdes.2021.112490

Cited by 34 publications

(14 citation statements)

References 19 publications

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“…It is limited by the surface water boiling which was, by the way, just recently overcome 12 . Testing survival under those extreme conditions (mostly using liquid metal heat shield 13 ) will be one of two major goals of tokamak COMPASS-Upgrade 14 , 15 , capable of reaching 100 MW/m 16 . This is, for better imagination, comparable to the Sun surface 63 MW/m radiation.…”

Section: Thermonuclear Fusion Reduction Due To Elm-induced Tungsten D...mentioning

confidence: 99%

Novel concept suppressing plasma heat pulses in a tokamak by fast divertor sweeping

Horáček

Lukes

Adámek

et al. 2022

Sci Rep

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One of the remaining challenges in magnetic thermonuclear fusion is survival of the heat shield protecting the tokamak reactor vessel against excessive plasma heat fluxes. Unmitigated high confinement edge localized mode (ELM) is a regular heat pulse damaging the heat shield. We suggest a novel concept of magnetic sweeping of the plasma contact strike point fast and far enough in order to spread this heat pulse. We demonstrate feasibility of a dedicated copper coil in a resonant circuit, including the induced currents and power electronics. We predict the DEMO ELM properties, simulate heat conduction, 3D particles motion and magnetic fields of the plasma and coil in COMSOL Multiphysics and Matlab. The dominant system parameter is voltage, feasible 18 kV yields 1 kHz sweeping frequency, suppressing the ELM-induced surface temperature rise by a factor of 3. Multiplied by other known mitigation concepts, ELMs might be mitigated enough to ensure safe operation of DEMO.

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Section: Thermonuclear Fusion Reduction Due To Elm-induced Tungsten D...mentioning

confidence: 99%

Novel concept suppressing plasma heat pulses in a tokamak by fast divertor sweeping

Horáček

Lukes

Adámek

et al. 2022

Sci Rep

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“…Recently, the final COMPASS experimental campaign was completed, the COMPASS tokamak was shut down in August 2021, and its disassembly has started. In parallel, preparations for the construction of the COMPASS Upgrade tokamak [62] proceeded through the final design phase and the COMPASS Upgrade related analysis, like the modelling of disruption forces [63] and of the NBI heating [64] were also presented at the 28th IAEA FEC. Therefore, the COMPASS experimental hall and related infrastructure is being evacuated at present and the experimental hall will modified to accommodate the new COMPASS Upgrade tokamak.…”

Section: Discussionmentioning

confidence: 99%

Overview of the COMPASS results ^*

et al. 2022

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COMPASS addressed several physical processes that may explain the behaviour of important phenomena. This paper presents results related to main fields of COMPASS research obtained in the recent two years, including studies of turbulence, L-H transition, plasma material interaction, runaway electron, and disruption physics:  Tomographic reconstruction of the edge/SOL turbulence observed by a fast visible camera allowed to visualize turbulent structures without perturbing the plasma. Dependence of the power threshold on the X-point height was studied and related role of radial electric field in the edge/SOL plasma was identified. The effect of high-field-side error fields on the L-H transition was investigated in order to assess the influence of the central solenoid misalignment and the possibility to compensate these error fields by low-field-side coils. Results of fast measurements of electron temperature during ELMs show the ELM peak values at the divertor are around 80% of the initial temperature at the pedestal. Liquid metals were used for the first time as plasma facing material in ELMy H-mode in the tokamak divertor. Good power handling capability was observed for heat fluxes up to 12 MW/m 2 and no direct droplet ejection was observed.  Partial detachment regime was achieved by impurity seeding in the divertor. The evolution of the heat flux footprint at the outer target was studied.  Runaway electrons were studied using new unique systems -impact calorimetry, carbon pellet injection technique, wide variety of magnetic perturbations. Radial feedback control was imposed on the beam.  Forces during plasma disruptions were monitored by a number of new diagnostics for vacuum vessel motion in order to contribute to the scaling laws of sideways disruption forces for ITER. Current flows towards the divertor tiles, incl. possible short-circuiting through PFCs, were investigated during the VDE experiments. The results support ATEC model and improve understanding of disruption loads.

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“…The hybrid probe concept is being developed and will be tested for qualification in various testing facilities, including fission research reactors and possibly upcoming fusion machines too, such as the divertor test tokamak facility (DTT) [64] and the COMPASS Upgrade tokamak [65].…”

Section: High Performance Hybrid Magnetic Sensorsmentioning

confidence: 99%

Long term operation of the radiation-hard Hall probes system and the path toward a high performance hybrid magnetic field sensor

Quercia

Pironti²,

Bolshakova³

et al. 2022

Nucl. Fusion

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The paper reports a systematic assessment of the Radiation-hard Hall Probes (RHP) magnetic diagnostic system of the JET tokamak, which is based on InSb semiconductor thin ﬁlms, and describes the path that lead to the proposal of an innovative magnetic probe concept. A relevant account of RHP operation during the recent Deuterium-Tritium experimental campaign (DTE2) is also provided, showing correct operation under ITER-like intense neutron ﬂux. The period considered for the systematic assessment of the RHP system ranges from October 2009 to March 2021, during which the machine produced more than 19000 pulses. The RHP system consists of six three-dimensional Hall probes, which have built-in recalibration capability, thanks to the presence of microsolenoids that produce a local known ﬁeld during a tailored automatic pre-pulse calibration sequence, that can also be initiated manually. During pulses, the microsolenoids can also be used as inductive sensors as their signals are recorded as well. Moreover, the system provides temperature measurements at the location of the probes, which are continuously recorded too. The assessment demonstrates accurate long-term operation of the RHP system. All the diagnostic channels reliably provide pre-pulse calibration data and pulse signals and the original sensitivities of the Hall sensors are preserved. Integration considerations and a data fusion analysis lead to the proposal of a high performance, compact, broadband, hybrid ﬁeld probe, consisting of the combination of an inductive coil and a Hall sensor, to be manufactured by means of the coil technology developed for ITER or an alternative concept with improved radiation-hardness. The hybrid probe is expected to deliver the advantages of both inductive and Hall sensing technologies, essentially in the same package size of a single ITER magnetic discrete probe. In particular, it would solve the problem of the drift of the integrator for long lasting burning plasma discharges. The signals produced by the coil and the Hall sensor, processed by means of a Luenberger-Kalman observer, provide a magnetic ﬁeld measurement which is non-drifting and low-noise. For these reasons, the hybrid probe has been proposed as the potential primary magnetic diagnostic sensor for future burning plasma experiments and demonstration fusion power plants.

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Preliminary design of the COMPASS upgrade tokamak

Cited by 34 publications

References 19 publications

Novel concept suppressing plasma heat pulses in a tokamak by fast divertor sweeping

Novel concept suppressing plasma heat pulses in a tokamak by fast divertor sweeping

Overview of the COMPASS results ^*

Long term operation of the radiation-hard Hall probes system and the path toward a high performance hybrid magnetic field sensor

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Preliminary design of the COMPASS upgrade tokamak

Cited by 34 publications

References 19 publications

Novel concept suppressing plasma heat pulses in a tokamak by fast divertor sweeping

Novel concept suppressing plasma heat pulses in a tokamak by fast divertor sweeping

Overview of the COMPASS results *

Long term operation of the radiation-hard Hall probes system and the path toward a high performance hybrid magnetic field sensor

Contact Info

Product

Resources

About

Overview of the COMPASS results ^*