Study on the new manufacture of ITER vacuum vessel thermal shield

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Kwanwoo Nam , Dongkwon Kang , Moohyun You , Myeongjun Kim , Sang-chul Kim , Chang Hyun Noh , Hyunsoo Kim , Kijung Jung
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引用次数: 0

Abstract

This paper describes the preparation and the status for the manufacturing of the new Vacuum Vessel Thermal Shield (VVTS) for ITER machine. As the delivered VVTS had the corrosion problem at the pipe weld, the VVTS was determined to be repaired and re-manufactured. The new VVTS has no silver coating and its pipe material is changed to exclude corrosion cracking at the cooling pipe. Roughness of the panel surface is reduced to have lower emissivity without silver coating. Several technical efforts to improve the pipe welding are presented in this paper. Stitch weld between the pipe and the panel is carefully tested with various specimens as Pre-Production Sample (PPS). Tack weld position is intended not to be overlapped with the stitch weld. Back shielding at the opposite side of the stitch weld is also applied to minimize the oxidation. Down-slope current of the welding machine is optimized for the pipe stitch weld. Heat correction method after the welding is investigated to confirm the soundness of the weld joint and the base metal. Impact test and corrosion test are performed for the specimens after the heat correction. All the manufactured VVTS panels are subjected to be leak-tested in a huge vacuum chamber with the pressurized cooling pipe with helium gas. Delivery status of the re-manufactured VVTS panels is presented and the anticipated manufacturing schedule are introduced in this paper.
本文介绍了为热核实验堆机器制造新真空容器隔热箱(VVTS)的准备工作和现状。由于已交付的 VVTS 在管道焊接处存在腐蚀问题,因此决定对 VVTS 进行修复和重新制造。新的 VVTS 没有银涂层,其管道材料也有所改变,以避免冷却管出现腐蚀裂纹。在没有银涂层的情况下,降低了面板表面的粗糙度,以降低辐射率。本文介绍了改进管道焊接的几项技术工作。管道和面板之间的搭接焊缝通过各种试样(PPS)进行了仔细测试。搭接焊缝的位置不能与缝合焊缝重叠。此外,还在缝合焊缝的另一侧进行背面保护,以尽量减少氧化。焊接机的下坡电流针对管道缝焊缝进行了优化。研究焊接后的热校正方法,以确认焊点和母材的完好性。对热校正后的试样进行冲击试验和腐蚀试验。所有制造出的 VVTS 面板都要在一个巨大的真空室中进行泄漏测试,并在冷却管中加入氦气进行加压。本文介绍了重新制造的 VVTS 面板的交付情况和预期制造时间表。
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
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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