{"title":"Steady-state Superconducting Advanced Spherical Tokamak Reactor (SASTR)","authors":"Yoshio Nagayama , Takaaki Fujita","doi":"10.1016/j.fusengdes.2025.114900","DOIUrl":null,"url":null,"abstract":"<div><div>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<sub>3</sub>Sn superconducting magnets, and a plasma current of 24.5 MA driven fully by the BS current.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"214 ","pages":"Article 114900"},"PeriodicalIF":1.9000,"publicationDate":"2025-03-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Fusion Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0920379625001024","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0
Abstract
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 Nb3Sn superconducting magnets, and a plasma current of 24.5 MA driven fully by the BS current.
期刊介绍:
The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.