Temperature dependence of sputtering yields of steels with various W content for plasma facing applications

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

Fusion Engineering and Design Pub Date : 2025-03-13 DOI:10.1016/j.fusengdes.2025.114950

S. Möller , M. Reinhart , B. Kuhn , A. Kreter

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Abstract

Materials are a key issue in any nuclear fusion reactor. For plasma-facing materials irradiation and sputtering limit their lifetime in a fusion power reactor. Steels allow for lower costs, reduced activation, and proven long irradiation lifetimes compared to tungsten at the expense of a lower sputtering lifetime.

Several studies investigated the connected effects showing W-fuzz like surface morphology and a W enrichment through preferential sputtering, opening up a potentially significant increase of this sputtering lifetime of steels.

The role of the W content in the steel is an open question. The presented exposure of 3 steels with W content from 0.5 to 2 at. % in deuterium plasma at 693–843 K sample temperature aims at resolving this. The experiments combine in-situ infrared imaging and passive spectroscopy with ex-situ ion-beam analysis.

At the given conditions, a flux density independent exponential W enrichment within 70 s time-constant followed by a 1400 s time-constant nano-structure formation is observed. The overall effect is a reduction of the Fe sputtering yield by a factor 4.4, 3.0, and 2.5 for 2 %, 1.1 %, 0.5 % W steels, respectively. This factor reduces slightly with temperature by up to 20 % towards higher temperatures.

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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.