Heating of SPIDER drivers during nominal operations: Calorimetry and numerical estimation

IF 2 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
S. Denizeau , D. López Bruna , P. Agostinetti , G. Berton , A. La Rosa , M. Pavei
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Abstract

SPIDER, the ion source prototype for ITER Neutral Beam Injectors, is under development at the Neutral Beam Test Facility (NBTF) in Padua, Italy. A first experimental campaign took place between 2018 and 2021. This paper focuses on the heating of SPIDER drivers during operations, primarily caused by RF power dissipation through eddy currents in passive structure elements. Specifically, it examines short pulses with low RF power (about 20 to 50 kW per driver) of the 2018–2021 campaign. It aims at validating the results of a 3D electromagnetic model that simulates RF coupling with plasma, by providing a realistic evaluation of driver temperature and incident power. A calorimetric study allows to estimate the share of RF power absorbed by the driver passive elements. In line with existing literature, results show that around 50% of the RF power is typically lost, with 90% of this loss occurring in the Faraday Shield Lateral Wall (FSLW). The second part of this study describes a self-consistent set of simulations to assess driver heating. Aforementioned electromagnetic code calculates the spatial distribution of power on the FSLW, and ANSYS Fluent models of the Faraday Shield cooling circuits are coupled with a thermal steady-state model that accounts for radiation, plasma heating and backstreaming ions (BSI). Three load cases are considered: low RF power without BSI (typical of 2018–2021 campaign), full target power, and a “worst-case scenario” with maximum RF power on the Faraday Shield. The temperature at which the mechanical properties of electrodeposited copper degrade is never exceeded. The electromagnetic code assumes constant electrical conductivity on the FSLW — that of copper at 50 °C. Thermal simulations support this hypothesis at low power but predict important variations of temperature — and therefore conductivity — at target conditions, locally modifying the RF coupling.
在标称操作期间的蜘蛛驱动器的加热:量热法和数值估计
SPIDER是ITER中性束注入器的离子源原型,目前正在意大利帕多瓦的中性束测试设施(NBTF)开发中。第一次实验活动在2018年至2021年之间进行。本文重点研究了SPIDER驱动器在工作过程中的发热问题,主要是由被动结构元件中涡流引起的射频功率耗散引起的。具体来说,它研究了2018-2021年运动中低射频功率(每个驱动器约20至50千瓦)的短脉冲。它旨在通过提供驱动器温度和入射功率的真实评估,验证模拟射频与等离子体耦合的3D电磁模型的结果。量热研究允许估计射频功率的份额吸收的驱动器无源元件。与现有文献一致,结果表明,大约50%的射频功率通常会损失,其中90%的损失发生在法拉第屏蔽侧壁(FSLW)中。本研究的第二部分描述了一组自一致的模拟来评估驾驶员加热。上述电磁代码计算了FSLW上功率的空间分布,并将法拉第屏蔽冷却电路的ANSYS Fluent模型与考虑辐射、等离子体加热和回流离子(BSI)的热稳态模型相结合。考虑了三种负载情况:无BSI的低射频功率(典型的2018-2021战役)、全目标功率和法拉第屏蔽上最大射频功率的“最坏情况”。不能超过电沉积铜的机械性能退化的温度。电磁代码假定FSLW上的电导率恒定-铜在50°C时的电导率。热模拟在低功率下支持这一假设,但预测了目标条件下温度的重要变化,从而改变了局部射频耦合。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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来源期刊
Fusion Engineering and Design
Fusion Engineering and Design 工程技术-核科学技术
CiteScore
3.50
自引率
23.50%
发文量
275
审稿时长
3.8 months
期刊介绍: The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.
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