钨基中氘的定量测定方法探讨

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
G.D. Soria , M. González , M. Roldán , G. García , D. Abejón-Arribas
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引用次数: 0

摘要

在本研究中,采用二次离子质谱法(SIMS),一种成熟有效的分析技术,探讨了定量钨中氘浓度的方法。在600 keV下注入三种不同氘影响的钨标准体,使用串流加速器制备,通过法拉第杯监测离子电流。为了评估D辐照对W试样的损伤程度,采用衍射和显微技术对辐照强度最高的W试样的微观结构和化学成分进行了分析。通过核反应分析(NRA)和硅测试器上的磁扇形SIMS进行互补测量,验证了氘定量的准确性。通过将信号与植入钨标准中的影响相关联,建立了校准曲线,实现了利用SIMS技术进行可靠的氘定量检测。所开发的方法对于理解氘在钨中的行为至关重要,钨是核聚变反应堆中关键的等离子体面材料,在核聚变反应堆中,准确的量化对于评估辐照损伤和氚库存管理方面的材料性能至关重要。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Approaching a deuterium quantitative determination methodology in tungsten matrices
In this research, a methodology for quantifying deuterium concentrations in tungsten is approached using secondary ion mass spectrometry (SIMS), a well-stablished and effective analytical technique. Tungsten standards implanted with three distinct deuterium fluences at 600 keV were prepared using a tandetron accelerator, monitoring the ion current via a Faraday cup. In order to assess the extent of damage caused by D irradiation, the microstructure and chemical composition of the W sample with the highest fluence were examined by diffraction and microscopy techniques. The precision of deuterium quantification was validated through complementary measurements performed via nuclear reaction analysis (NRA) and magnetic sector SIMS on Si testers. A calibration curve was established by correlating signals with the implanted fluences in the tungsten standards, enabling reliable quantitative deuterium detection using SIMS technique. The approach developed is critical for understanding deuterium behavior in tungsten, a key plasma-facing material in nuclear fusion reactors, where accurate quantification is essential for evaluating material performance in terms of irradiation damage and tritium inventory management.
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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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