The ARIES Advanced And Conservative Tokamak (ACT) Power Plant Study
Authors: Charles E. Kessel, et. al.
Abstract: Tokamak power plants are studied with advanced and conservative design philosophies
in order to identify the impacts on the resulting designs and to provide guidance to
critical research needs. Incorporating updated physics understanding, and using more
sophisticated engineering and physics analysis, the tokamak configurations have
developed a more credible basis compared to older studies. The advanced configuration
assumes a self-cooled lead lithium (SCLL) blanket concept with SiC composite structural
material with 58% thermal conversion efficiency. This plasma has a major radius of 6.25
m, a toroidal field of 6.0 T, a q95 of 4.5, a βN total of 5.75, H98 of 1.65, n/nGr of 1.0, and
peak divertor heat flux of 13.7 MW/m2. The conservative configuration assumes a dual
coolant lead lithium (DCLL) blanket concept with ferritic steel structural material and
helium coolant, achieving a thermal conversion efficiency of 45%. The plasma major
radius is 9.75 m, a toroidal field of 8.75 T, a q95 of 8.0, a βN
total of 2.5, H98 of 1.25, n/nGr of 1.3, and peak divertor heat flux of 10 MW/m2. The divertor heat flux treatment with a
narrow power scrape-off width has driven the plasmas to larger major radius. Edge and
divertor plasma simulations are targeting a basis for high radiated power fraction in the
divertor, which is necessary for solutions to keep the peak heat flux in the range of 10-15
MW/m2. Combinations of the advanced and conservative approaches show intermediate
sizes. A new systems code using a database approach has been used and shows that the
operating point is really an operating zone with some range of plasma and engineering
parameters and very similar costs of electricity. Papers in this issue provide more
detailed discussion of the work summarized here.
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Accepted for publication in: Fusion Science and Technology; AIRES-ACT special issue, January 2015
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Download PPPL-5008 (pdf KB pp)
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