In-situ measurement of tritium accumulation and decontamination of tungsten

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

Fusion Engineering and Design Pub Date : 2025-04-23 DOI:10.1016/j.fusengdes.2025.115041

Dominic Batzler, Max Aker, James Robert Braun, Robin Größle, Philipp Haag, Marco Röllig, Dylan Ray Roodt, Marie-Christine Schäfer, Marius Schaufelberger

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Abstract

Tritium accumulation on surfaces, also known as the memory effect, has a wide range of implications for operating and maintaining fusion reactors, astroparticle physics experiments using tritium, and tritium analytics. At Tritium Laboratory Karlsruhe (TLK), the Tritium Activity Chamber Experiment (TRACE) was designed and built to investigate the tritium memory effect of a variety of materials. With TRACE, it is possible to expose samples to high-purity tritium at ambient temperature and measure their retained near-surface activity in-situ via beta-induced X-ray spectrometry (BIXS). Within this work, the relative memory effect of two tungsten samples — one pre-contaminated — after a cumulative exposure to tritium of 2100 mbar

\cdot

h was determined. The time evolutions of their activity prove the repeatability of the experiment. Attempts were made to decontaminate one of the samples in-situ. During continuous evacuation, merely 20% of its near-surface activity could be desorbed at a bake-out temperature of 200 °C.

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钨的氚累积和去污的原位测量

氚在表面的积累，也被称为记忆效应，对核聚变反应堆的操作和维护、使用氚的天体粒子物理实验和氚分析有广泛的影响。在卡尔斯鲁厄氚实验室（TLK），设计并建造了氚活性室实验（TRACE），以研究各种材料的氚记忆效应。使用TRACE，可以将样品暴露在环境温度下的高纯度氚中，并通过β诱导x射线光谱法（BIXS）原位测量其保留的近地表活性。在这项工作中，测定了两个钨样品-一个预污染-在累积暴露于2100 mbar⋅h的氚后的相对记忆效应。它们活动的时间演变证明了实验的可重复性。试图对其中一个样品进行原位净化。在连续抽离过程中，在200°C的烘烤温度下，其近表面活性仅能解吸20%。

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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.