DTT真空容器热屏蔽的热-力学分析

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

Fusion Engineering and Design Pub Date : 2025-04-27 DOI:10.1016/j.fusengdes.2025.115090

S. Del Nero , M. Fulici , G. Barone , R. Bonifetto , M. Dalla Palma , P. Fanelli

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引用次数: 0

摘要

采用有限元分析方法，对托卡马克导流器试验（DTT）项目中真空容器（VV）和真空容器隔热罩（VVTHS）在热载荷和管道诱导应力作用下的热结构行为进行了评价。三手烟由两个外壳组成，分别称为内三手烟和外三手烟，冷却管（CPs）焊接在最里面。VV和THS通过约束相对位移的螺栓进行机械耦合。采用壳单元模拟VV和VVTHS，梁单元模拟CPs和螺栓，耦合方程模拟螺栓连接，建立了有限元模型。该分析结合了材料的温度依赖特性和应用于VV的周期性循环条件。研究结果可以深入了解各部件的位移和应力分布，为DTT VVTHS系统的结构完整性和未来的设计优化提供信息。

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Thermo-mechanical analysis of DTT Vacuum Vessel Thermal Shield

The Thermo-structural behavior of the Vacuum Vessel (VV) and Vacuum Vessel Thermal Shield (VVTHS) of the Divertor Tokamak Test (DTT) project under thermal loads and piping-induced stresses was evaluated using Finite Element Analysis (FEA). The THS consists of two shells, respectively referred as inner THS and outer THS, with Cooling Pipes (CPs) welded to the innermost. The VV and THS are mechanically coupled by using bolts that constrain relative displacements. A Finite Element Model (FEM) was developed using shell elements for VV and VVTHS, beam elements for CPs and bolts, and coupling equations to simulate bolted connections. The analysis incorporated temperature-dependent material properties and periodic cycling conditions for applied on VV. Results provide insight into the displacement and stress distributions across the components, informing the structural integrity and future design optimization of the DTT VVTHS system.

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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.