Heat Flux Calculations on NSTX-U and STs with New HYPERION Code*

NSTX-U will operate with a plasma current of up to 2 MA for 5 seconds and neutral beam injection (NBI) heating up to 10 MW. The safe operation of the plasma-facing components (PFCs) requires a large coverage of IR diagnostics that view the PFCs and the capability to accurately calculate the heat flux on target. HYPERION is a new 2-D heat flux calculation code for calculating heat flux incident on axisymmetric divertors. We present recent verification tests of HYPERION that show exceptional agreement with NSTX heat flux calculated by TACO <!--[if supportFields]>style='font-size:12.0pt;line-height:107%;font-family:"Times New Roman",serif;
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Gan2013169[1]169app="EN" db-id="ettzp0tr70fx5peat995ftsrxw02evex9xzf"
timestamp="1638981474">169name="Journal
Article">17K.
F. GanJ-W. AhnJ.-W.
ParkR. MaingiA. G.
McLeanT. K. GrayX.
GongX. D.
Zhang2D
divertor heat flux distribution using a 3D heat conduction solver in National
Spherical Torus ExperimentReview of
Scientific InstrumentsReview
of Scientific
Instruments0235058422013https://aip.scitation.org/doi/abs/10.1063/1.479259510.1063/1.4792595style='mso-element:field-separator'>[1] and DIII-D heat flux calculated by the THEODOR code <!--[if supportFields]>style='mso-spacerun:yes'> ADDIN EN.CITE
Herrmann1995209[2]209app="EN" db-id="ettzp0tr70fx5peat995ftsrxw02evex9xzf"
timestamp="1667235525">209name="Journal Article">17A.
HerrmannW. JunkerK.
GuntherS. BoschM.
KaufmannJ. NeuhauserG.
PautassoTh, RichterR.
SchneiderEnergy
flux to the ASDEX-Upgrade diverter plates determined by thermography and
calorimetryPlasma Physics and Controlled
FusionPlasma
Physics and Controlled
Fusion1737119951995/01/010741-3335https://dx.doi.org/10.1088/0741-3335/37/1/00210.1088/0741-3335/37/1/002style='mso-element:field-separator'>[2]. We also discuss future developments for HYPERION that will use OpenFOAM to solve the inverse heat conduction problem on 3D PFCs, and discuss calculations of heat flux for NSTX-U and spherical tokamak operation.

[1] K. F. Gan et al., "2D divertor heat flux distribution using a 3D heat conduction solver in National Spherical Torus Experiment," Review of Scientific Instruments, vol. 84, no. 2, p. 023505, 2013, doi: 10.1063/1.4792595.

[2] A. Herrmann et al., "Energy flux to the ASDEX-Upgrade diverter plates determined by thermography and calorimetry," Plasma Physics and Controlled Fusion, vol. 37, no. 1, p. 17, 1995/01/01 1995, doi: 10.1088/0741-3335/37/1/002.