DTT ECH传输线单光束反射镜的热结构分析

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design Pub Date : 2025-04-23 DOI:10.1016/j.fusengdes.2025.115088

A. Salvitti , A. Moro , A. Bruschi , G. Calabrò , F. Fanale , P. Fanelli , S. Garavaglia , G. Granucci , S. Meloni , P. Platania , A. Romano

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引用次数: 0

摘要

转移托卡马克试验（DTT）设施的电子回旋加热（ECH）是其加热等离子体的主要系统，装机功率为32兆瓦。一个ECH集群由1 MW/170 GHz源（8个回旋管）、一条准光传输线（TL）和两个天线组成。TL有效地将由回旋管产生的微波光束传输到发射器。基于准光学概念，TL采用反射镜传输光束。它在概念上划分的三个部分之一是回旋管大厅（SBG）中的单光束部分，其中光束以独立的光路传播。由于欧姆损耗，一小部分光束功率被反射镜吸收，导致SBG反射镜吸收的总功率为~ 1-2 kW。镜面温度升高，产生变形。镜面标称形状的损失会降低传输效率，影响确保光束传播系统有效性能的标称参数。对不同的SBG反射镜进行了概念设计，模拟了其热结构行为。镜面通过设计为可变螺距的细长螺旋通道进行主动水冷却，最高温度可达28°C，变形低（~ 23 μm），证明了冷却系统的有效性。最后，如果有必要，同样的方法应用于厚度的参数分析，以评估最佳性能。这表明，对厚度的初始假设似乎是一个有充分根据的选择。

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Thermo-structural analysis on the DTT ECH Transmission Line Single-Beam mirrors

The Electron Cyclotron Heating (ECH) of the Divertor Tokamak Test (DTT) facility is its main system to heat the plasma with an installed power of 32 MW. A cluster of the ECH consists of 1 MW/170 GHz sources (8 gyrotrons), a quasi-optical Transmission Line (TL) and two antennas. The TL efficiently transmits the microwave beams, produced by gyrotrons, up to the launchers. Based on the quasi-optical concept, the TL employs mirrors for the transmission of the beams. One of the three segments in which it is conceptually divided is a Single-Beam section in the Gyrotron hall (SBG), where the beams propagate with an independent optical path. A small fraction of beam power is absorbed by the reflecting mirror due to ohmic losses, resulting in a total power absorbed by an SBG mirror of ∼1-2 kW. The mirror temperature increases, generating deformations. The loss of the nominal shape of the mirror can contribute to reducing the transmission efficiency, compromising the nominal parameters that ensure the effective performance of the beam propagation system. The conceptual design of different SBG mirrors is carried out, simulating the thermal-structural behaviour. The mirrors, actively water-cooled through channels designed as elongated spirals with variable pitch, achieve maximum temperatures of 28 °C and low deformations (∼23 μm), demonstrating the effectiveness of the cooling system. In the end, the same method is then applied in a parametric analysis of the thickness to evaluate the best performance, if necessary. It showed that the initial assumption on the thickness appears to be a well-founded choice.

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来源期刊

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.