Detection of absorbed neutrons through determination of rhenium content in tungsten with laser induced fast pulse discharge

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
B.D. Stankov , I. Traparić , M. Gavrilović Božović , M. Ivković
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Abstract

The diagnostics of the first wall of future fusion reactors provides a major source of information about the state of the machine and the expected lifetime of the first wall components. As the absorption of neutrons can cause induced radioactivity of the first wall tiles and produce significant structural changes to material, it is of the essence to monitor the amount of absorbed neutrons. One possibility to monitor them is via nuclear transmutation reaction where tungsten absorbs neutron and creates rhenium core. Therefore by assessing the amount of rhenium present in the material, information about neutron irradiation conditions can be deduced. Hence in this work, in order to assess the concentration of rhenium, Laser Induced Breakdown Spectroscopy (LIBS) combined with Fast Pulse Discharge (FPD) was used. The main achievement of this work is the amplification of line intensity and signal to noise ratio compared to the classical LIBS setup at reduced pressure which enables detection of Re in samples with less than 0.1% at of Re. With synergistic use of LIBS and FPD, ie. Laser Induced Fast Pulse Discharge (LIFPD), significantly enhanced Limit Of Detection (LOD) is obtained compared to the previously reported results. This result is of particular importance since only small amounts of rhenium are expected to be found in the first wall tiles, therefore making this approach suitable for this type of diagnostics.

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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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