{"title":"Parameter Space Constraints for Compact Spherical Tokamak Fusion Reactors","authors":"P. N. Maya, S. P. Deshpande","doi":"10.1080/15361055.2023.2247854","DOIUrl":null,"url":null,"abstract":"AbstractParameter space for spherical tokamak reactors is explored quantitatively to elucidate the main constraints for spherical tokamak design choices. Using a constant plasma current Ip search constraint, a set of four Ip scenarios (5, 10, 15, and 20 MA) is first explored in a wide parameter space. Considering modest but gradually increasing auxiliary power, a set of four machine configurations (major radius R = 1.25, 1.75, 2.25, and 3.5 m) is explored next, optimizing the Ip and the bootstrap fraction. Constraints that narrow down the vast parameter space are elaborated along with critical assumptions, such as current drive efficiency, H-mode enhancement factor, nuclear shielding efficiency, and confinement scaling. Limits on the current density of the center post and how it affects the shielding are quantitatively indicated, thereby setting a lower limit on the aspect ratio.Keywords: Fusion power plantspherical tokamakreactor designsystems codescoping studies AcknowledgmentsThe authors would like to acknowledge the help rendered during the preparation of the manuscript by Research Scholar Piyush Prajapati. We also thank the IPR HPC (ANTYA) team for their help. The authors also would like to acknowledge the anonymous reviewers for their valuable suggestions for improving the quality of the paper.Disclosure StatementNo potential conflict of interest was reported by the authors.","PeriodicalId":12626,"journal":{"name":"Fusion Science and Technology","volume":"65 1","pages":"0"},"PeriodicalIF":0.9000,"publicationDate":"2023-10-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Fusion Science and Technology","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.1080/15361055.2023.2247854","RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q3","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0
Abstract
AbstractParameter space for spherical tokamak reactors is explored quantitatively to elucidate the main constraints for spherical tokamak design choices. Using a constant plasma current Ip search constraint, a set of four Ip scenarios (5, 10, 15, and 20 MA) is first explored in a wide parameter space. Considering modest but gradually increasing auxiliary power, a set of four machine configurations (major radius R = 1.25, 1.75, 2.25, and 3.5 m) is explored next, optimizing the Ip and the bootstrap fraction. Constraints that narrow down the vast parameter space are elaborated along with critical assumptions, such as current drive efficiency, H-mode enhancement factor, nuclear shielding efficiency, and confinement scaling. Limits on the current density of the center post and how it affects the shielding are quantitatively indicated, thereby setting a lower limit on the aspect ratio.Keywords: Fusion power plantspherical tokamakreactor designsystems codescoping studies AcknowledgmentsThe authors would like to acknowledge the help rendered during the preparation of the manuscript by Research Scholar Piyush Prajapati. We also thank the IPR HPC (ANTYA) team for their help. The authors also would like to acknowledge the anonymous reviewers for their valuable suggestions for improving the quality of the paper.Disclosure StatementNo potential conflict of interest was reported by the authors.
期刊介绍:
Fusion Science and Technology, a research journal of the American Nuclear Society, publishes original research and review papers on fusion plasma physics and plasma engineering, fusion nuclear technology and materials science, fusion plasma enabling science technology, fusion applications, and fusion design and systems studies.