Flat-top plasma operational space of the STEP power plant

Author:

Tholerus E.ORCID,Casson F.J.ORCID,Marsden S.P.ORCID,Wilson T.ORCID,Brunetti D.ORCID,Fox P.ORCID,Freethy S.J.ORCID,Hender T.C.,Henderson S.S.ORCID,Hudoba A.ORCID,Kirov K.K.ORCID,Koechl F.ORCID,Meyer H.ORCID,Muldrew S.I.ORCID,Olde C.,Patel B.S.ORCID,Roach C.M.ORCID,Saarelma S.ORCID,Xia G.ORCID,

Abstract

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.

Funder

Culham Centre for Fusion Energy

Publisher

IOP Publishing

Reference106 articles.

1. The European roadmap towards fusion electricity

2. STEP-on the pathway to fusion commercialization;(the STEP team),2020

3. The physics of the preferred plasma scenario for STEP;Meyer H for the STEP Plasma, Control and Heating & Current Drive Team and Contributors,2022

4. Conceptual design workflow for the STEP Prototype Powerplant

5. Ideal MHD stability limits of low aspect ratio tokamak plasmas

Cited by 3 articles. 订阅此论文施引文献 订阅此论文施引文献,注册后可以免费订阅5篇论文的施引文献,订阅后可以查看论文全部施引文献

1. Plasma burn—mind the gap;Philosophical Transactions of the Royal Society A: Mathematical, Physical and Engineering Sciences;2024-08-26

2. Controlling a new plasma regime;Philosophical Transactions of the Royal Society A: Mathematical, Physical and Engineering Sciences;2024-08-26

3. On the importance of parallel magnetic-field fluctuations for electromagnetic instabilities in STEP;Nuclear Fusion;2024-07-03

同舟云学术

1.学者识别学者识别

2.学术分析学术分析

3.人才评估人才评估

"同舟云学术"是以全球学者为主线,采集、加工和组织学术论文而形成的新型学术文献查询和分析系统,可以对全球学者进行文献检索和人才价值评估。用户可以通过关注某些学科领域的顶尖人物而持续追踪该领域的学科进展和研究前沿。经过近期的数据扩容,当前同舟云学术共收录了国内外主流学术期刊6万余种,收集的期刊论文及会议论文总量共计约1.5亿篇,并以每天添加12000余篇中外论文的速度递增。我们也可以为用户提供个性化、定制化的学者数据。欢迎来电咨询!咨询电话:010-8811{复制后删除}0370

www.globalauthorid.com

TOP

Copyright © 2019-2024 北京同舟云网络信息技术有限公司
京公网安备11010802033243号  京ICP备18003416号-3