Chapter 9: ITER contributions for Demo plasma development
Chapter 9: ITER contributions for Demo plasma development
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DOI：
10.1088/0029-5515/47/6/s09
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发表时间：
2007-06
期刊：
影响因子：
3.3
通讯作者：
V. Mukhovatov;M. Shimada;K. Lackner;D. Campbell;N. Uckan;J. Wesley;T. Hender;B. Lipschultz;A. Loarte;R. Stambaugh;R. Goldston;Y. Shimomura;M. Fujiwara;M. Nagami;V. Pustovitov;H. Zohm;ITPA CC Members;ITPA Topical Group Chairs and Co-Chairs-ITPA-Topical-Group-Chairs-and-Co-Chairs-2271995195;the ITER International Team
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文献类型：
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作者：
V. Mukhovatov;M. Shimada;K. Lackner;D. Campbell;N. Uckan;J. Wesley;T. Hender;B. Lipschultz;A. Loarte;R. Stambaugh;R. Goldston;Y. Shimomura;M. Fujiwara;M. Nagami;V. Pustovitov;H. Zohm;ITPA CC Members;ITPA Topical Group Chairs and Co-Chairs-ITPA-Topical-Group-Chairs-and-Co-Chairs-2271995195;the ITER International Team
本章总结了物理问题的示范环形聚变发电厂（演示），可以解决ITER操作。这些问题包括燃烧等离子体的具体问题，即高能粒子行为和等离子体自热效应，以及在目前的实验中无法完全解决的更广泛的一类发电厂规模的物理问题。Demo的一个关键问题是由快粒子驱动的MHD和高能粒子模式是否会变得不稳定并影响等离子体性能。自加热效应预计将是特别重要的内部传输势垒（ITBs）和高自举电流分数的稳态等离子体的控制。ITER的实验数据将大大改善主要等离子体参数的演示预测的物理基础，例如能量约束时间，β和密度限制，边缘基座温度和密度，以及ELM和中断引起的容器内组件的热负荷。ITER还将作为聚变技术研究的试验台，如发电厂等离子体诊断、加热和电流驱动系统、面向等离子体的组件、偏滤器和包层模块。最后，国际热核实验堆预计将提供其他磁约束计划的燃烧等离子体行为的理解的好处。
The chapter summarizes the physics issues of the demonstration toroidal fusion power plant (Demo) that can be addressed by ITER operation. These include burning plasma specific issues, i.e. energetic particle behaviour and plasma self-heating effects, and a broader class of power-plant scale physics issues that cannot be fully resolved in present experiments. A critical issue for Demo is whether MHD and energetic particle modes driven by fast particles will become unstable and affect plasma performance. Self-heating effects are expected to be especially important for control of steady-state plasmas with internal transport barriers (ITBs) and high bootstrap current fractions. Experimental data from ITER will improve strongly the physics basis of projections to Demo of major plasma parameters such as the energy confinement time, beta and density limits, edge pedestal temperature and density, and thermal loads on in-vessel components caused by ELMs and disruptions. ITER will also serve as a test bed for fusion technology studies, such as power plant plasma diagnostics, heating and current drive systems, plasma facing components, divertor and blanket modules. Finally, ITER is expected to provide benefits for the understanding of burning plasma behaviour in other magnetic confinement schemes.