Physics design point of high-field stellarator reactors

被引:18
作者
Alonso, J. A. [1 ]
Calvo, I [1 ]
Carralero, D. [1 ]
Velasco, J. L. [1 ]
Garcia-Regana, J. M. [1 ]
Palermo, I [1 ]
Rapisarda, D. [1 ]
机构
[1] CIEMAT, Lab Nacl Fus, Av Complutense 40, Madrid 28040, Spain
关键词
stellarator reactor; stellarator optimization; high-field fusion reactor; ENERGY CONFINEMENT; TRITIUM BALANCE; DENSITY LIMIT; POWER-PLANT; COMPACT; PLASMA;
D O I
10.1088/1741-4326/ac49ac
中图分类号
O35 [流体力学]; O53 [等离子体物理学];
学科分类号
070204 ; 080103 ; 080704 ;
摘要
The ongoing development of electromagnets based on high temperature superconductors has led to the conceptual exploration of high-magnetic-field fusion reactors of the tokamak type, operating at on-axis fields above 10 T. In this work we explore the consequences of the potential future availability of high-field three-dimensional electromagnets on the physics design point of a stellarator reactor. We find that, when an increase in the magnetic field strength B is used to maximally reduce the device linear size R similar to B (-4/3) (with otherwise fixed magnetic geometry), the physics design point is largely independent of the chosen field strength/device size. A similar degree of optimization is to be imposed on the magnetohydrodynamic, transport and fast ion confinement properties of the magnetic configuration of that family of reactor design points. Additionally, we show that the family shares an invariant operation map of fusion power output as a function of the auxiliary power and relative density variation. The effects of magnetic field over-engineering and the R(B) scaling of design points with constant neutron wall loading are also inspected. In this study we use geometric parameters characteristic of the helical axis advanced stellarator reactor, but most results apply to other stellarator configurations.
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页数:19
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