A compact tokamak design uses high-temperature superconducting coils to reach on axis

PHYSICS · Multi-part · Fermi University Physics · Plasma Physics · Fusion plasmas · Fusion plasmas

Energy from Physics, Ch Fusion as a power plant: gain, beta, wall loading and breeding

Problem

A compact tokamak design uses high-temperature superconducting coils to reach B=12 TB = 12\,\mathrm{T} on axis, while holding the plasma beta to β=0.020\beta = 0.020 at an ion temperature of 10 keV10\,\mathrm{keV}, with equal deuterium and tritium densities. Take the Bosch-Hale rate coefficient at 10 keV10\,\mathrm{keV} as ⟨σv⟩=1.14×10−22 m3 s−1\langle\sigma v\rangle = 1.14\times10^{-22}\,\mathrm{m^3\,s^{-1}} and the energy released per D-T fusion as 17.6 MeV17.6\,\mathrm{MeV}. ((a)) Find the plasma pressure and the total ion density. ((b)) Find the fusion power density. ((c)) State how many times this exceeds ITER's design power density of 0.6 MW m−30.6\,\mathrm{MW\,m^{-3}}.

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