热核实验堆转向镜组件和电子回旋加速器加热与电流驱动致动器局部控制系统的初步控制导向建模

IF 1.9 4区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Journal of Fusion Energy Pub Date : 2024-10-29 DOI:10.1007/s10894-024-00465-0
G. Grapow, T. Ravensbergen, M. D’Onorio, F. Pesamosca, A. Vu, G. Carannante
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引用次数: 0

摘要

热核实验堆电子回旋加速器加热和电流驱动器(ECH)在加热和控制聚变等离子体方面发挥着关键作用,而转向镜则是该驱动器的重要组成部分。在开发和验证等离子体控制系统(PCS)的过程中,必须要有一个具有代表性的 ECH 模型。本手稿旨在以瑞士等离子体中心测试的设计为基础,提出一个面向控制的转向镜模型。在这种设计中,转向镜在一组外部加压波纹管与预压弹簧的作用下,在一些无摩擦挠性枢轴上旋转。该系统被称为转向镜组件(SMA)。考虑到热核实验堆的最新要求,通过将模拟结果与实验结果进行比较,对模型的一致性进行了测试。在精度方面普遍提高的性能与原型结果一致。
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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Preliminary Control-Oriented Modeling of the ITER Steering Mirror Assembly and Local Control System in the Electron Cyclotron Heating & Current Drive Actuator

The ITER Electron Cyclotron Heating and Current Drive (ECH) plays a pivotal role in heating and controlling fusion plasmas, with the Steering Mirrors being a crucial component of this actuator. A representative model of the ECH is compulsory in the development and validation of the Plasma Control System (PCS). This manuscript aims to propose a Control-Oriented model of the Steering Mirrors based on the design tested at the Swiss Plasma Centre. In this design a steering mirror rotates on some frictionless flexure pivots due to the action of a set of externally pressurized bellows acting against pre-compressed springs. This system is referred to as the Steering Mirror Assembly (SMA). The adherence of the model is tested by comparing the simulations with the experimental results, while considering ITER’s most recent requirements. Performances, generally increased in terms of accuracy, are in line with the prototype’s results.

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来源期刊
Journal of Fusion Energy
Journal of Fusion Energy 工程技术-核科学技术
CiteScore
2.20
自引率
0.00%
发文量
24
审稿时长
2.3 months
期刊介绍: The Journal of Fusion Energy features original research contributions and review papers examining and the development and enhancing the knowledge base of thermonuclear fusion as a potential power source. It is designed to serve as a journal of record for the publication of original research results in fundamental and applied physics, applied science and technological development. The journal publishes qualified papers based on peer reviews. This journal also provides a forum for discussing broader policies and strategies that have played, and will continue to play, a crucial role in fusion programs. In keeping with this theme, readers will find articles covering an array of important matters concerning strategy and program direction.
期刊最新文献
Research on Insulation Technology for Nb3Sn Layer Coil of Superconducting Conductor Testing Facility Preliminary Control-Oriented Modeling of the ITER Steering Mirror Assembly and Local Control System in the Electron Cyclotron Heating & Current Drive Actuator High Energy Density Radiative Transfer in the Diffusion Regime with Fourier Neural Operators Retraction Note: Determination of the Plasma Internal Inductance and Evaluation of its Effects on Plasma Horizontal Displacement in IR-T1 Tokamak Effects of Injected Current Streams on MHD Equilibrium Reconstruction of Local Helicity Injection Plasmas in a Spherical Tokamak
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