Advancements of testing activities for development of in-bore welding tool for large feeding pipes of in-vessel components

IF 2 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design Pub Date : 2025-07-26 DOI:10.1016/j.fusengdes.2025.115367

Donato Sorgente , Rocco Salvato , Vincenzo Claps , Christian Bachmann , Günter Janeschitz , Rocco Mozzillo

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引用次数: 0

Abstract

This work presents the results of welding tests made on large pipes (DN200) in austenitic stainless steel AISI316L to be used in the nuclear fusion DEMOnstration power plant, DEMO. Samples were designed and manufactured to physically simulate the coupling and the alignment of the two pipes and their joining by an in-bore welding system. The trajectories describing the movement of the TIG torch during the operation were selected for the specific geometric configuration where the multi-pass operation has to start from the outer diameter of the pipe and to proceed inwards. The temperature in the material close to the welding zone was monitored before and after each welding pass. The shielding gas (argon) was used on the top of the weld seam and, in a specific ad-hoc set of tests, also on the back side (back shielding) in order to check the need to protect the rear (external) part of the weld seam during the first passes. Destructive tests were then carried out to preliminarily assess the quality of the joint. Several pieces of information were collected including suitable process parameters, the time required to complete the individual joint and wear of the tungsten electrode.

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大型船内构件进料管道内焊工具研制试验工作进展

本文介绍了用于核聚变示范电厂（DEMO）的AISI316L奥氏体不锈钢DN200大管的焊接试验结果。设计并制造了样品，以物理模拟两根管道的耦合和对准以及它们通过内孔焊接系统的连接。描述TIG炬在操作过程中的运动轨迹是为特定的几何配置选择的，其中多道操作必须从管道外径开始并向内进行。在每道焊前和焊后监测靠近焊接区的材料温度。在焊缝顶部使用保护气体（氩气），在一组特定的临时测试中，也在背面（背面保护）使用保护气体，以检查在第一次通过时是否需要保护焊缝的后部（外部）部分。然后进行了破坏试验，初步评价了接头的质量。收集了合适的工艺参数、完成单个接头所需的时间和钨电极的磨损等信息。

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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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.