MITICA束流源仿真软件2024电气后绝缘子的结构特性

IF 2 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
B. Spolaore , S. Denizeau , G. Chitarin , M. Valente , A. Rizzolo , G. Berton , M. Dalla Benetta , N. De Rossi
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引用次数: 0

摘要

先前在MITICA束流源(BS)上进行的研发活动确定需要对其加速器的真空中1 MV高压(HV)保持进行实验验证,使用全尺寸模型来再现与高压保持相关的MITICA BS外部几何形状。本文描述了该模型的一个关键结构部件的分析和测试,称为“后绝缘体”。该组件由聚醚醚酮(PEEK)制成,这是一种工程热塑性塑料,具有加速器级之间的电绝缘体和承载实体模型悬臂结构的机械支撑的双重功能。作为承受高负荷的关键部件,采用实验设计的方法,对实验施工前进行的PEEK绝缘体进行了规范设计和分析设计。在分析中,使用两个有限元模型模拟了PEEK后绝缘子的应力-应变模式,以评估其在运行过程中的行为,并支持对后续试验结果的解释。第一个模型使用精确的几何形状,包括螺钉、螺纹插入件和螺栓连接,用于将PEEK后绝缘体固定到不锈钢法兰上。第二种型号是简化版,其中绝缘子和法兰直接连接的粘接接触型。利用单轴水力试验系统和特定的试验装置,对4个后绝缘子试样进行了实验测试,以建立该构件在拉弯应力精确组合下的准静态力学行为。试验结果是肯定的,但与实验数据相比,数值推导的刚度估计过高。这种差异在总变形、等效应力和MITICA模拟BS的固有频率方面产生了影响。通过将拉伸试验的数值模型与实验结果进行比对,量化了这些差异,并用实际绝缘子刚度重新进行了结构模拟。最后,通过开发M14螺钉、螺纹插入件和PEEK块材料的精确子模型,研究了这种差异的解释,显示了与实际情况相比,螺纹插入件连接与粘合连接的建模如何高估了模型的刚度。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Structural behavior of electrical post-insulators for the MITICA Beam Source Mock-Up SOFT 2024
Previous R&D activities conducted on the MITICA Beam Source (BS) identified the need for an experimental validation of the 1 MV High Voltage (HV) holding in vacuum of its accelerator, using a full size Mock-up that reproduces the external geometry of MITICA BS relevant for HV holding. This paper describes the analyses and tests of a critical structural component of this Mock-Up, referred to as “post-insulators”. This component is made of PolyEtherEtherKetone (PEEK), an engineering thermoplastic, and has a double-function of electrical insulator between the stages of the accelerator and of mechanical support carrying the cantilevered structure of the Mock-Up. Being critical components withstanding high loads, a Design by Experiment approach has been followed to complete the Design by Code and Design by Analysis of the PEEK insulators conducted before the construction of the experiment.
In the analyses, the stress–strain pattern of the PEEK post-insulators is simulated using two FEM models, so as to evaluate the behavior during operation and to support the interpretation of the results obtained during subsequent tests. A first model uses accurate geometry, including screws, threaded inserts and bolts connections used to fasten the PEEK post-insulator to the stainless-steel flanges. The second model is a simplified version, where insulator and flanges are connected directly with bonded contact type.
Experimental tests are performed on four post-insulator samples, using a uni-axial hydraulic test system and a particular test set-up, in order to establish the quasi-static mechanical behavior of the component under a precise combination of tensile-bending stress.
The test results are positive, however, the numerically-derived stiffness is overestimated compared to the experimental data. Such discrepancy has consequences in terms of total deformations, equivalent stress and natural frequencies of the MITICA Mock-Up BS. These differences have been quantified by calibrating the numerical models of the tensile test with the experimental results, and the Mock-Up structural simulations have been re-ran with the real insulator stiffness. Lastly, an explanation for this discrepancy is investigated by developing an accurate sub model of the M14 screw, threaded insert and PEEK bulk material, showing how modeling the screw-threaded insert connections with bonded connections overestimates the stiffness of the model compared to the real-case scenario.
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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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