Flat-top plasma operational space of the STEP power plant

IF 3.5 1区 物理与天体物理 Q1 PHYSICS, FLUIDS & PLASMAS
E. Tholerus, F.J. Casson, S.P. Marsden, T. Wilson, D. Brunetti, P. Fox, S.J. Freethy, T.C. Hender, S.S. Henderson, A. Hudoba, K.K. Kirov, F. Koechl, H. Meyer, S.I. Muldrew, C. Olde, B.S. Patel, C.M. Roach, S. Saarelma, G. Xia, the STEP team1
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Abstract

STEP is a spherical tokamak prototype power plant that is being designed to demonstrate net electric power. The design phase involves the exploitation of plasma models to optimise fusion performance subject to satisfying various physics and engineering constraints. A modelling workflow, including integrated core plasma modelling, MHD stability analysis, SOL and pedestal modelling, coil set and free boundary equilibrium solvers, and whole plant design, has been developed to specify the design parameters and to develop viable scenarios. The integrated core plasma model JETTO is used to develop individual flat-top operating points that satisfy imposed criteria for fusion power performance within operational constraints. Key plasma parameters such as normalised beta, Greenwald density fraction, auxiliary power and radiated power have been scanned to scope the operational space and to derive a collection of candidate non-inductive flat-top points. The assumed auxiliary heating and current drive is either from electron cyclotron (EC) systems only or a combination of EC and electron Bernstein waves. At present stages of transport modelling, there is a large uncertainty in overall confinement for relevant parameter regimes. For each of the two auxiliary heating and current drive systems scenarios, two candidate flat-top points have been developed based on different confinement assumptions, totalling to four operating points. A lower confinement assumption generally suggests operating points in high-density, high auxiliary power regimes, whereas higher confinement would allow access to a broader parameter regime in density and power while maintaining target fusion power performance.
STEP 电站的平顶等离子体运行空间
STEP 是一个球形托卡马克原型电站,其设计目的是演示净电力。设计阶段包括利用等离子体模型来优化聚变性能,同时满足各种物理和工程限制条件。已经开发了一个建模工作流程,包括综合核心等离子体建模、MHD 稳定性分析、SOL 和基座建模、线圈组和自由边界平衡求解器以及整个电站设计,以指定设计参数并开发可行的方案。综合核心等离子体模型 JETTO 用于开发单个平顶运行点,以满足在运行限制条件下聚变功率性能的既定标准。对关键等离子体参数(如归一化贝他值、格林沃尔德密度分数、辅助功率和辐射功率)进行了扫描,以确定运行空间的范围,并得出一系列候选非感应平顶点。假定的辅助加热和电流驱动要么仅来自电子回旋加速器(EC)系统,要么结合了电子回旋加速器和电子伯恩斯坦波。在目前的传输建模阶段,相关参数区的总体约束存在很大的不确定性。对于两种辅助加热和电流驱动系统方案中的每一种方案,都根据不同的约束假设开发了两个候选平顶点,总共有四个运行点。较低的约束假设一般建议在高密度、高辅助功率状态下的运行点,而较高的约束将允许在保持目标聚变功率性能的同时,进入密度和功率方面更宽泛的参数状态。
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来源期刊
Nuclear Fusion
Nuclear Fusion 物理-物理:核物理
CiteScore
6.30
自引率
39.40%
发文量
411
审稿时长
2.6 months
期刊介绍: Nuclear Fusion publishes articles making significant advances to the field of controlled thermonuclear fusion. The journal scope includes: -the production, heating and confinement of high temperature plasmas; -the physical properties of such plasmas; -the experimental or theoretical methods of exploring or explaining them; -fusion reactor physics; -reactor concepts; and -fusion technologies. The journal has a dedicated Associate Editor for inertial confinement fusion.
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