Steady-state Superconducting Advanced Spherical Tokamak Reactor (SASTR)

• A concept of Superconducting steady-state Advanced Spherical Tokamak Reactor (SASTR) wit slim-CS is proposed. • The plasma current can be fully driven by the boot-strap (BS) current and the thermal energy is sustained by the alpha heating in a SASTR with the reversed-shear type internal transport barrier (RS-ITB). • By investigating SASTR using a set of plasma burning equations, the toroidal magnetic field and the confinement enhancement factor are key parameters for satisfying the beta limit and density limit criteria, respectively. • We present a conceptual design of a 0.8 GWe SASTR power reactor with a major radius of 4.5 m, an aspect ratio of 1.8, a toroidal field of 2.67 T generated by Nb 3 Sn superconducting magnets. A concept for a Steady-state Superconducting Advanced Spherical Tokamak Reactor (SASTR) with a slim-CS is proposed. This is a spherical tokamak (ST) with an internal transport barrier (ITB) and superconducting magnets. The ITB allows for sufficient bootstrap (BS) current to sustain the plasma. The feasibility of a self-sustained SASTR is investigated by using a set of plasma burning equations. We find that the toroidal magnetic field and the confinement enhancement factor are key parameters to meet the beta limit and density limit criteria, respectively. We estimate the dependence of the cost of electricity (COE) on the aspect ratio and reactor size. We present a conceptual design of a 0.8 GWe SASTR power reactor with a major radius of 4.5 m, an aspect ratio of 1.8, a toroidal field of 2.67 T generated by Nb 3 Sn superconducting magnets, and a plasma current of 24.5 MA driven fully by the BS current.

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Publication Details

Journal
Fusion Engineering and Design
Published
2025-03-05
DOI
https://doi.org/10.1016/j.fusengdes.2025.114900
Primary Topic
Magnetic confinement fusion research
Type
article
Field-Weighted Citation Impact
0.00

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article

Steady-state Superconducting Advanced Spherical Tokamak Reactor (SASTR)

Yoshio Nagayama, Takao Fujita
Fusion Engineering and Design
Magnetic confinement fusion research
article

Steady-state Superconducting Advanced Spherical Tokamak Reactor (SASTR)

Yoshio Nagayama, Takao Fujita
article en

Abstract

• A concept of Superconducting steady-state Advanced Spherical Tokamak Reactor (SASTR) wit slim-CS is proposed. • The plasma current can be fully driven by the boot-strap (BS) current and the thermal energy is sustained by the alpha heating in a SASTR with the reversed-shear type internal transport barrier (RS-ITB). • By investigating SASTR using a set of plasma burning equations, the toroidal magnetic field and the confinement enhancement factor are key parameters for satisfying the beta limit and density limit criteria, respectively. • We present a conceptual design of a 0.8 GWe SASTR power reactor with a major radius of 4.5 m, an aspect ratio of 1.8, a toroidal field of 2.67 T generated by Nb 3 Sn superconducting magnets. A concept for a Steady-state Superconducting Advanced Spherical Tokamak Reactor (SASTR) with a slim-CS is proposed. This is a spherical tokamak (ST) with an internal transport barrier (ITB) and superconducting magnets. The ITB allows for sufficient bootstrap (BS) current to sustain the plasma. The feasibility of a self-sustained SASTR is investigated by using a set of plasma burning equations. We find that the toroidal magnetic field and the confinement enhancement factor are key parameters to meet the beta limit and density limit criteria, respectively. We estimate the dependence of the cost of electricity (COE) on the aspect ratio and reactor size. We present a conceptual design of a 0.8 GWe SASTR power reactor with a major radius of 4.5 m, an aspect ratio of 1.8, a toroidal field of 2.67 T generated by Nb 3 Sn superconducting magnets, and a plasma current of 24.5 MA driven fully by the BS current.

Fusion Engineering and DesignVol. 214
National Institute for Fusion Science (JP), Nagoya University (JP)
National Institute for Fusion Science
Affordable and clean energy
Openalex Percentile: Top 97%
Magnetic confinement fusion research
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Steady-state Superconducting Advanced Spherical Tokamak Reactor (SASTR) — Yoshio Nagayama, Takao Fujita · Fusion Engineering and Design (2025) | TGRS Research Map | TGRS