紧凑球形托卡马克聚变反应堆的参数空间约束

IF 0.9 4区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY Fusion Science and Technology Pub Date : 2023-10-09 DOI:10.1080/15361055.2023.2247854
P. N. Maya, S. P. Deshpande
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引用次数: 0

摘要

摘要定量探讨了球形托卡马克反应堆的参数空间,阐明了球形托卡马克设计选择的主要制约因素。利用恒定等离子体电流Ip搜索约束,首先在宽参数空间中探索了一组四种Ip场景(5、10、15和20 MA)。考虑适度但逐渐增加的辅助功率,接下来探索一组四种机器配置(主半径R = 1.25, 1.75, 2.25和3.5 m),优化Ip和bootstrap分数。详细阐述了缩小巨大参数空间的约束条件以及关键假设,如电流驱动效率、h模增强因子、核屏蔽效率和约束尺度。对中心柱的电流密度的限制及其对屏蔽的影响进行了定量指示,从而设定了宽高比的下限。关键词:核聚变电站球形托卡马克反应堆设计系统代码解析研究鸣谢感谢研究学者Piyush Prajapati在论文准备过程中提供的帮助。我们也感谢IPR HPC (ANTYA)团队的帮助。作者也要感谢匿名审稿人为提高论文质量提出的宝贵建议。披露声明作者未报告潜在利益冲突。
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Parameter Space Constraints for Compact Spherical Tokamak Fusion Reactors
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.
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来源期刊
Fusion Science and Technology
Fusion Science and Technology 工程技术-核科学技术
CiteScore
2.00
自引率
11.10%
发文量
60
审稿时长
3 months
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.
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