The tokamak system code D0FUS and its first applications: Impact of B and confinement scaling law on power plant design

IF 2 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Timothé Auclair, Eric Nardon, Yanick Sarazin, Jean-François Artaud, Baptiste Boudes, Clarisse Bourdelle, Jean-Luc Duchateau, Alexandre Torre
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引用次数: 0

Abstract

D0FUS is a new system code written in Python and designed to enable fast, extensive, and easily interpretable parameter scans. Inspired by the approach of Freidberg et al. (2015), D0FUS computes the main plasma stability indicators as well as the associated radial build. The code’s architecture and capabilities are reviewed, and its governing equations are presented. First results show possible viable designs at large aspect ratio, explore possible operations at high magnetic field and highlight the critical role of the energy confinement time scaling laws.
托卡马克系统代码D0FUS及其首次应用:B和约束标度律对电厂设计的影响
D0FUS是一个用Python编写的新系统代码,旨在实现快速、广泛和易于解释的参数扫描。受Freidberg等人(2015)方法的启发,D0FUS计算主要等离子体稳定性指标以及相关的径向构建。本文回顾了代码的体系结构和功能,并给出了其控制方程。第一个结果显示了在大宽高比下可能可行的设计,探索了在高磁场下可能的操作,并突出了能量约束时间标度定律的关键作用。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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来源期刊
Fusion Engineering and Design
Fusion Engineering and Design 工程技术-核科学技术
CiteScore
3.50
自引率
23.50%
发文量
275
审稿时长
3.8 months
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.
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