The scoping, design, and plasma physics optimization of the Eos neutron source stellarator

On the path to a fusion pilot plant, Thea Energy plans to build Eos, a sub-breakeven, deuterium-deuterium, beam-target fusion, stellarator neutron source facility for producing tritium and other valuable radioisotopes. In this paper, a set of 1D plasma physics models are coupled and used to design t...

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Main Authors: C.P.S. Swanson, D.A. Gates, S.T.A. Kumar, M.F. Martin, T.G. Kruger, D.W. Dudt, P.J. Bonofiglo, the Thea Energy team
Format: Article
Language:English
Published: IOP Publishing 2025-01-01
Series:Nuclear Fusion
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Online Access:https://doi.org/10.1088/1741-4326/ada56a
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author C.P.S. Swanson
D.A. Gates
S.T.A. Kumar
M.F. Martin
T.G. Kruger
D.W. Dudt
P.J. Bonofiglo
the Thea Energy team
author_facet C.P.S. Swanson
D.A. Gates
S.T.A. Kumar
M.F. Martin
T.G. Kruger
D.W. Dudt
P.J. Bonofiglo
the Thea Energy team
author_sort C.P.S. Swanson
collection DOAJ
description On the path to a fusion pilot plant, Thea Energy plans to build Eos, a sub-breakeven, deuterium-deuterium, beam-target fusion, stellarator neutron source facility for producing tritium and other valuable radioisotopes. In this paper, a set of 1D plasma physics models are coupled and used to design the operating point of the facility and predict performance. At this foundational stage of the design, analytic and approximate models are sufficient to capture the leading-order effects, and fast enough to run in the inner loop of an optimizer. Higher-fidelity analyses will follow. Models of 1D profile-dependent neutral beam stopping, ion beam slowing down, beam-target fusion, electron-ion classical heat transfer, energy confinement (ISS04), beam pressure, beam heating of ions and electrons, beam-beam fusion fraction, and neutral beam injection and gyrotron heating electrical efficiencies are included. A numerical optimizer is used to determine the minimum required facility electric power to generate tritium at a given rate. A potentially advantageous regime is described in which modern precisely-quasisymmetric stellarators, new high-temperature superconductors, ITER-derived neutral beam injection, and new high-frequency gyrotrons enable a suitible target plasma with hot electrons, cold ions, peaked density and temperature profiles, and high beam-injected ion density. It appears possible at this time for a facility with a medium-scale and medium-strength stellarator whose required facility electric power is less than 40 MW to produce $2.5\times 10^{17}$ neutrons s ^−1 for the production of radioisotopes. With the addition of a tritium breeding blanket, such a facility could produce 0.2 grams d ^−1 or 70 grams yr ^−1 of tritium.
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spelling doaj-art-6a1af764ba1c44a693fb4aa098c324732025-01-28T12:17:39ZengIOP PublishingNuclear Fusion0029-55152025-01-0165202605310.1088/1741-4326/ada56aThe scoping, design, and plasma physics optimization of the Eos neutron source stellaratorC.P.S. Swanson0https://orcid.org/0000-0003-0231-8525D.A. Gates1https://orcid.org/0000-0001-5679-3124S.T.A. Kumar2https://orcid.org/0000-0002-6444-5178M.F. Martin3https://orcid.org/0000-0003-2032-2894T.G. Kruger4https://orcid.org/0000-0003-1462-3033D.W. Dudt5https://orcid.org/0000-0002-4557-3529P.J. Bonofiglo6https://orcid.org/0000-0001-5057-7383the Thea Energy team7Thea Energy, Inc. , Kearny, NJ, United States of AmericaThea Energy, Inc. , Kearny, NJ, United States of AmericaThea Energy, Inc. , Kearny, NJ, United States of AmericaThea Energy, Inc. , Kearny, NJ, United States of AmericaThea Energy, Inc. , Kearny, NJ, United States of AmericaThea Energy, Inc. , Kearny, NJ, United States of AmericaPrinceton Plasma Physics Laboratory , Princeton, NJ, United States of AmericaThea Energy, Inc. , Kearny, NJ, United States of AmericaOn the path to a fusion pilot plant, Thea Energy plans to build Eos, a sub-breakeven, deuterium-deuterium, beam-target fusion, stellarator neutron source facility for producing tritium and other valuable radioisotopes. In this paper, a set of 1D plasma physics models are coupled and used to design the operating point of the facility and predict performance. At this foundational stage of the design, analytic and approximate models are sufficient to capture the leading-order effects, and fast enough to run in the inner loop of an optimizer. Higher-fidelity analyses will follow. Models of 1D profile-dependent neutral beam stopping, ion beam slowing down, beam-target fusion, electron-ion classical heat transfer, energy confinement (ISS04), beam pressure, beam heating of ions and electrons, beam-beam fusion fraction, and neutral beam injection and gyrotron heating electrical efficiencies are included. A numerical optimizer is used to determine the minimum required facility electric power to generate tritium at a given rate. A potentially advantageous regime is described in which modern precisely-quasisymmetric stellarators, new high-temperature superconductors, ITER-derived neutral beam injection, and new high-frequency gyrotrons enable a suitible target plasma with hot electrons, cold ions, peaked density and temperature profiles, and high beam-injected ion density. It appears possible at this time for a facility with a medium-scale and medium-strength stellarator whose required facility electric power is less than 40 MW to produce $2.5\times 10^{17}$ neutrons s ^−1 for the production of radioisotopes. With the addition of a tritium breeding blanket, such a facility could produce 0.2 grams d ^−1 or 70 grams yr ^−1 of tritium.https://doi.org/10.1088/1741-4326/ada56anuclear fusionstellaratorbeam-target fusionfusion neutron sourcefusion system studiesneutral beam injection
spellingShingle C.P.S. Swanson
D.A. Gates
S.T.A. Kumar
M.F. Martin
T.G. Kruger
D.W. Dudt
P.J. Bonofiglo
the Thea Energy team
The scoping, design, and plasma physics optimization of the Eos neutron source stellarator
Nuclear Fusion
nuclear fusion
stellarator
beam-target fusion
fusion neutron source
fusion system studies
neutral beam injection
title The scoping, design, and plasma physics optimization of the Eos neutron source stellarator
title_full The scoping, design, and plasma physics optimization of the Eos neutron source stellarator
title_fullStr The scoping, design, and plasma physics optimization of the Eos neutron source stellarator
title_full_unstemmed The scoping, design, and plasma physics optimization of the Eos neutron source stellarator
title_short The scoping, design, and plasma physics optimization of the Eos neutron source stellarator
title_sort scoping design and plasma physics optimization of the eos neutron source stellarator
topic nuclear fusion
stellarator
beam-target fusion
fusion neutron source
fusion system studies
neutral beam injection
url https://doi.org/10.1088/1741-4326/ada56a
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