README date: January 19, 2022

Content:  ARK digital data for Nuclear Fusion paper "Fusion Pilot Plant performance and the role of a Sustained High Power Density tokamak"

Authors: J.E. Menard, B.A. Grierson, T. Brown, C. Rana, Y. Zhai, F.M. Poli, R. Maingi, W. Guttenfelder, P.B. Snyder

NOTE:  All variable descriptions and units are included in the CSV and TXT files 
and match the units in the 16 figures in the paper. 

Figure 1. Confinement time normalized by ITER confinement scaling, fusion power, 
auxiliary heating power, plasma major radius, total TF coil volume, and blanket 
change-out volume versus aspect ratio for FPPs with 100MWe net electric.
Figure_01.csv
Figure_01.png

Figure 2. Self-driven current fraction fself versus volume-averaged pressure <p> 
and fself versus Scrape-Off Layer (SOL) parallel heat flux parameter q||0-sep
Figure_02.csv
Figure_02.png

Figure 3. Fusion triple product versus plasma pulse duration from Fig. 4.2 in 
Reference 3 and Fig. 3.16 in Reference 44 adapted to show the proposed baseline 
SHPD initial operation and a long-pulse upgrade option.
Figure_03.png

Figure 4. Projected SHPD performance versus aspect ratio and major radius for 
Petty08 confinement scaling and PNNBI = 50MW.
Figure_04.csv
Figure_04.png

Figure 5. Projected L-H mode threshold power versus aspect ratio, auxiliary heating 
power normalized by L-H threshold power, and power to separatrix normalized by 
threshold power for SHPD facilities (Paux = 50MW, 30% core radiation fraction) 
with R=1.0 to 1.8m and FPP facilities.
Figure_05.csv
Figure_05.png

Figure 6. Preliminary plasma shaping scan, facility cross section, and 
preliminary liquid metal divertor concepts.
Figure_06a.csv
Figure_06b.csv
Figure_06.png

Figure 7. Local peak stresses near shear pins, and local stress at TF limbs 
along the region of vertical ports. 
Figure_07.png

Figure 8. Total plasma pressure, and current versus NNBI tangency radius 
for A=2.0 and 2.5.
Figure_08.csv
Figure_08.jpg

Figure 9. Steady-state temperature, density, and pressure profiles and 
current density profiles for A=2.0.
Figure_09a.csv
Figure_09b.csv
Figure_09.jpg

Figure 10. Bootstrap fraction and fast-ion pressure fraction versus 
Greenwald fraction for A=2.0 configuration.
Figure_10.csv
Figure_10.png

Figure 11. TORAY simulation of current drive for A=2.0 using 170 GHz fundamental O-mode.  
A single upper-outside launch location at 60º counter-clockwise from outside midplane.
Figure_11.csv
Figure_11.png

Figure 12. TORAY simulations of total driven current as a function of launch position 
for a single launch position as the launch position moves from outside midplane to 
the top of the machine.  At each launch location poloidal and toroidal steering are 
varied to determine the maximum driven current.
Figure_12.csv
Figure_12.png

Figure 13. Electron and ion temperature and electron density and current density 
and safety factor during ECCD.
Figure_13a.csv
Figure_13b.csv
Figure_13.jpg

Figure 14. Eich and Chang parameterizations of the SOL heat flux width versus aspect 
ratio for FPP and SHPD configurations with R=1.0m to 1.8m.   
Figure_14.csv
Figure_14.png

Figure 15. Projected upstream separatrix Te and ne, integrated radiative loss function 
LINT for nitrogen, and projected nitrogen and neon impurity density fractions for divertor 
detachment for FPP and SHPD configurations.
Figure_15.csv
Figure_15.jpg

Figure 16. Plasma boundary and first-wall/limiter surface including lower divertor layout. 
Parallel and perpendicular heat flux and total field angle of incidence values at inboard 
and outboard divertor vertical targets for an A=2.0 SHPD device with R=1.34m and kappa=2.24. 
Figure_16a.csv
Figure_16b.txt
Figure_16c.txt
Figure_16.jpg