外推法
电磁线圈
可预测性
核工程
托卡马克
物理
计算机科学
等离子体
计算物理学
核物理学
统计
数学
工程类
量子力学
作者
M. Pharr,N.C. Logan,C. Paz-Soldan,J.K. Park,C. Hansen
出处
期刊:Nuclear Fusion
[IOP Publishing]
日期:2024-09-24
卷期号:64 (12): 126025-126025
标识
DOI:10.1088/1741-4326/ad7ed6
摘要
Abstract 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.
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