Repair of heat load damaged plasma–facing material using the wire-based laser metal deposition process

IF 2.3 2区 物理与天体物理 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Jannik Tweer , Robin Day , Thomas Derra , Daniel Dorow-Gerspach , Stefan Gräfe , Marcin Rasinski , Marius Wirtz , Christian Linsmeier , Thomas Bergs , Ghaleb Natour
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Abstract

Due to its unique properties tungsten is a promising candidate as plasma-facing-material (PFM) in future nuclear fusion reactors. Tungsten features an exceptionally high melting point, high thermal conductivity, low tritium inventory and comparatively low erosion rate under plasma loading [1]. But given the extreme loads on the PFM during operation of a fusion reactor, the lifetime of plasma-facing components (PFC)s is limited. Currently, it is planned to replace damaged PFCs when they reach the end of their service life. However, the lifetime of PFCs could be increased by in situ repair using additive manufacturing technology (AM) in the form of direct-energy-deposition (DED). The wire–based laser metal deposition process (LMD-w) meets several necessary conditions for operation in the vessel and could be used for performing such in situ repairs.
It was investigated if the LMD-w process is able to heal thermal induced surface cracks and roughening by remelting the substrate during deposition of tungsten. For this purpose, tungsten samples of 12 × 12 × 5 mm3, which later served as substrate plates for the LMD-w experiments, were treated with combined steady-state and transient thermal loads in the electron beam facility JUDITH 2. These samples were brazed to a copper cooling structure and exposed to 105 thermal shocks of 0.5 ms duration and an intensity of Labs = 0.55 GW m−2 (FHF = 12 MW s0.5 m−2) at a base temperature of Tbase = 700 °C. This way, edge localized mode (ELM) like thermal load damage was induced on the tungsten samples. On these samples, different LMD-w and laser remelting process strategies were performed. Subsequently, these samples were analyzed, and it was examined that the healing of the pre-damaged substrate material was successful. In parallel, the laser remelting process was modeled in a thermal transient finite element method (FEM) simulation in order to gain an insight into the temperatures prevailing in the material during the process.
利用线基激光金属沉积工艺修复热负荷损坏的等离子体面材料
由于其独特的性能,钨有望成为未来核聚变反应堆中面向等离子体的材料(PFM)。钨具有极高的熔点、高导热性、低氚存量,以及在等离子体负载下相对较低的侵蚀率[1]。但鉴于聚变反应堆运行期间对 PFM 的极端负荷,面向等离子体的部件(PFC)的使用寿命有限。目前,计划在损坏的 PFC 达到使用寿命时对其进行更换。不过,通过使用直接能量沉积(DED)形式的增材制造技术(AM)进行原位修复,可以延长 PFC 的使用寿命。基于线材的激光金属沉积工艺(LMD-w)符合在容器中操作的几个必要条件,可用于执行此类原位修复。我们研究了 LMD-w 工艺是否能够通过在钨沉积过程中重熔基体来愈合热引起的表面裂纹和粗化。为此,在 JUDITH 2 电子束设备中对 12 × 12 × 5 mm3 的钨样品(后来用作 LMD-w 实验的基板)进行了稳态和瞬态热负荷组合处理。 这些样品被钎焊到铜冷却结构上,并在基底温度 Tbase = 700 °C 的条件下受到 105 次持续时间为 0.5 ms、强度为 Labs = 0.55 GW m-2 (FHF = 12 MW s0.5 m-2)的热冲击。这样就在钨样品上诱发了类似热负荷损伤的边缘局部模式(ELM)。在这些样品上执行了不同的 LMD-w 和激光重熔工艺策略。随后,对这些样品进行了分析,结果表明预损伤基底材料的愈合是成功的。同时,对激光重熔过程进行了热瞬态有限元法(FEM)模拟建模,以便深入了解过程中材料的普遍温度。
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
Nuclear Materials and Energy
Nuclear Materials and Energy Materials Science-Materials Science (miscellaneous)
CiteScore
3.70
自引率
15.40%
发文量
175
审稿时长
20 weeks
期刊介绍: The open-access journal Nuclear Materials and Energy is devoted to the growing field of research for material application in the production of nuclear energy. Nuclear Materials and Energy publishes original research articles of up to 6 pages in length.
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