Power and particle exhaust for the Infinity Two fusion pilot plant

An analysis of the divertor designs for the Infinity Two fusion pilot plant (FPP) baseline plasma design is presented. The divertor uses an $m=5$ , $n=4$ magnetic island chain, where m is the poloidal number and n is the toroidal number. Two divertor designs are presented. A classical divertor that is similar to the Wendelstein 7-X island divertor is analyzed using diffusive field-line following and the fluid code EMC3-Lite . For a baseline $800\text{ MW}$ operating point in Infinity Two, the conditions where the heat flux on the divertor plate remains in the acceptable region are analyzed. In addition a related, but different and novel large island backside divertor (LIBD) design is shown. The LIBD promises improved neutral pumping by closing the divertor through the use of baffling and with a structure inside the island, thus preventing neutralized plasma particles from reente ring the plasma.

Authors

Publication Details

Journal
Journal of Plasma Physics
Published
2025-03-24
DOI
https://doi.org/10.1017/s0022377825000273
Citations
6
Primary Topic
Magnetic confinement fusion research
Type
article
Field-Weighted Citation Impact
11.22
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article

Power and particle exhaust for the Infinity Two fusion pilot plant

J.M. Canik, T. S. Pedersen, Ashoke De, Karen Willis et al.
6 citations
Journal of Plasma Physics
Magnetic confinement fusion research
11.22
article

Power and particle exhaust for the Infinity Two fusion pilot plant

J.M. Canik, T. S. Pedersen, Ashoke De, Karen Willis, W. Guttenfelder, P. Sinha, A. Bader, C. C. Hegna, D. Velez, Jeffrey W. Talley, Annelise Malkus, A. Ayilaran, M. Knilans
article en
6 citations

Abstract

An analysis of the divertor designs for the Infinity Two fusion pilot plant (FPP) baseline plasma design is presented. The divertor uses an $m=5$ , $n=4$ magnetic island chain, where m is the poloidal number and n is the toroidal number. Two divertor designs are presented. A classical divertor that is similar to the Wendelstein 7-X island divertor is analyzed using diffusive field-line following and the fluid code EMC3-Lite . For a baseline $800\text{ MW}$ operating point in Infinity Two, the conditions where the heat flux on the divertor plate remains in the acceptable region are analyzed. In addition a related, but different and novel large island backside divertor (LIBD) design is shown. The LIBD promises improved neutral pumping by closing the divertor through the use of baffling and with a structure inside the island, thus preventing neutralized plasma particles from reente ring the plasma.

Journal of Plasma PhysicsVol. 91(2)
Openalex Percentile: Top 2%
Magnetic confinement fusion research
11.22
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Power and particle exhaust for the Infinity Two fusion pilot plant — J.M. Canik, T. S. Pedersen, et al. · Journal of Plasma Physics (2025) | TGRS Research Map | TGRS