Abstract
A Faraday wheel (FW)—an electric generator of constant electrical polarity that produces huge currents—could be implemented in an existing tokamak to study high-gain high-field (HGHF) fusion plasma, such as the Experimental Advanced Superconducting Tokamak (EAST). HGHF plasma can be realized in EAST by updating its pulsed-power system to compress plasma in two steps by induction fields; high gains of the Lawson trinity parameter and fusion power are both predicted by formulating the HGHF plasma. Both gain rates are faster than the decrease rate of the plasma volume. The formulation is checked by earlier ATC tests. Good agreement between theory and tests indicates that scaling to over 10 T at EAST may be possible by two-step compressions with a compression ratio of the minor radius of up to 3. These results point to a quick new path of fusion plasma study, i.e., simulating the Sun by EAST.
Highlights
Tokamaks, the most complex and unusual transformers in the world, have been, or are being, implemented at EAST7 (Experimental Advanced Superconducting Tokamak, the original HT-7U established by China in 1998), DIII-D, KSTAR, JT60-SA, JET and ITER to study magnetic confinement fusion (MCF) energy[8,9]
A Faraday wheel (FW) with two-step magnetic compressions is suggested for insertion in the existing tokamak to scale up the plasma parameter to a new level, a high-gain high-field (HGHF) state within the plasma, which may facilitate the exploration of fusion energy
Its basic mechanism has been preliminary proven by the Adiabatic Toroidal Compressor (ATC) and TFTR with one-step major-radius magnetic compression, dubbed the Artsimovich-Furth-Ellis axisymmetric magnetic pumping scheme[13,14,15,16,17]
Summary
The most complex and unusual transformers in the world, have been, or are being, implemented at EAST7 (Experimental Advanced Superconducting Tokamak, the original HT-7U established by China in 1998), DIII-D, KSTAR, JT60-SA, JET and ITER to study magnetic confinement fusion (MCF) energy[8,9]. The ITER 400-s H-mode was simulated by EAST over 30 s, providing a foundation for the development of attractive and feasible fusion power plants, such as ITER7,12 or CFETR (Chinese Fusion Engineering Test Reactor). These facilities only consider classical D-shaped plasma in tokamaks for approaching the ignition parameters of plasma and do not incorporate the merits of the Faraday wheel (FW). A FW with two-step magnetic compressions is suggested for insertion in the existing tokamak to scale up the plasma parameter to a new level, a high-gain high-field (HGHF) state within the plasma, which may facilitate the exploration of fusion energy. The scheme has been collected, formulated and extended here for high-gain plasma accommodated in a conventional D-shaped vacuum vessel, such as in EAST, DIII-D or JET9
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