热核实验堆托卡马克上端口 #18 垂直中子照相机诊断系统在电磁、液压、热和地震负荷下的强度分析

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

Fusion Engineering and Design Pub Date : 2024-11-22 DOI:10.1016/j.fusengdes.2024.114733

D.B. Gin , B. Coriton , F. Josseaume , S. Pak , P. Ruiz , I.V. Buslakov , I.D. Kirienko , A.M. Lobachev , V.S. Modestov , I.R. Murtazin , G.E. Nemtsev , S.B. Stepanov , M.V. Ivantsivskiy , A.S. Taskaev , P.A. Seleznev , N.A. Zolotukhina , J. Kim

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引用次数: 0

摘要

该研究分析了名为 "上垂直中子照相机（UVNC）"的独特诊断系统在不同性质负载下的强度特性。UVNC 包括一个 DN10 水冷系统、六个探测器单元、电气馈入件和电缆。考虑了机械、热、地震和电磁负荷的组合。多物理过程在 ANSYS 软件中执行，先前获得的电磁和地震载荷数据以及正常运行和烘烤模式下的热场数据在本研究中用作机械配方的初始数据。结构分析结果表明，在保持运行特性的同时，模型的主要结构元素具有足够的安全系数。文章描述并论证了在极端中子通量、高热负荷和综合机械应力条件下开发系统的全新设计，同时考虑到了热核实验堆设施的所有独特运行因素。

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Strength analysis of the Upper Vertical Neutron Camera diagnostic system of the ITER Tokamak Upper Port # 18 under electromagnetic, hydraulic, thermal, and seismic loads

The study is an analysis of the strength properties of a unique diagnostic system called Upper Vertical Neutron Camera (UVNC) under the loads of various nature. The UVNC includes a DN10 water cooling system, six detector units, electrical feedthroughs, and cables. Combinations of mechanical, thermal, seismic and electromagnetic loads were considered. The implementation of multiphysical processes is carried out in ANSYS Software, and the previously obtained data on electromagnetic and seismic loads, as well as thermal fields in Normal Operation and Baking modes are used in this study as initial data for mechanical formulations. The results of the structural analysis demonstrate a sufficient margin of safety of the main structural elements of the model while maintaining operational properties. In the article described and justified totally new design of developing system under extreme neutron fluxes, high thermal loads, and combined mechanical stresses, taking into account all the unique operational factors of the ITER facility.

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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.