返回
Error field predictability and consequences for ITER
DOI:10.1088/1741-4326/ad7ed6.png)
摘要
En 中文
ITER coil tolerances are re-evaluated using the modern understanding of coupling to least-stable plasma modes and an updated center-line-traced model of ITER's coil windings. This reassessment finds the tolerances to be conservative through a statistical, linear study of n = 1 error fields (EFs) due to tilted, shifted misplacements and nominal windings of central solenoid and poloidal field coils within tolerance. We also show that a model-based correction scheme remains effective even when metrology quality is sub-optimal, and compare this to projected empirical correction schemes. We begin with an analysis of the necessity of error field correction (EFC) for daily operation in ITER using scalign laws for the EF penetration threshold. We then consider the predictability of EF dominant mode overlap across early planned ITER scenarios and, as measuring EFs in high power scenarios can pose risks to the device, the potential for extrapolation to the ITER Baseline Scenario (IBS). We find that carefully designing a scenario matching currents proportionally to those of the IBS is far more important than plasma shape or profiles in accurately measuring an optimal correction current set.
Keyword:
ITER
magnetohydrodynamics
tokamak
error field
magnetic island
期刊
IF:
4
论文数:
9.3K
被引数:
2.2W
机构
引用论文
TokaMaker: An open-source time-dependent Grad-Shafranov tool for the design and modeling of axisymmetric fusion devicesTokaMaker: 用于轴对称融合设备的设计和建模的开源时间相关grad-shafranov工具
Tailoring tokamak error fields to control plasma instabilities and transport
NATURE COMMUNICATIONS
IF15.7

