Preliminary Physics Motivation and Engineering Design Assessment of the National High Power Torus

Robert D. Woolley

关键词: DESIGN;    DIVERTORS;    FLEXIBILITY;    HEAT FLUX;    PERFORMANCE;    PHYSICS;    PLASMA;    POWER PLANTS;    RETENTION Scoping;    Steady-State Fusion Reactors;   

DOI  :  10.2172/958405
RP-ID  :  PPPL-4416
PID  :  OSTI ID: 958405
Others  :  TRN: US1000022

学科分类：原子、分子光学和等离子物理

美国|英语

来源: SciTech Connect

【 摘 要 】

In April 2006, Dr. Ray Orbach, Director of the DOE Office of Science, challenged the fusion community to "propose a new facility... which will put the U.S. at the lead in world fusion science." Analysis of the gaps between expected ITER performance and the requirements of a demonstration power plant (Demo) pointed to the critical and urgent need to develop fusion-relvant plasma-material interface (PMI) solutions consistent with sustained high plasma performance. A survey of world fusion program indicated that present and planned experimental devices do not advance the PMI issue beyond ITER, and a major dedicated experimental facility is warranted. Such a facility should provide the flexibility and access needed to solve plasma boundary challenges related to divertor heat flux and particle exhaust while also developing methods to minimize hydrogenic isotope retention and remaining compatible with high plasma performance.