Measurement of uranium and fission products in a spent fuel sample using fiber-optic laser-induced breakdown spectroscopy

IF 3.3 2区 化学 Q2 CHEMISTRY, ANALYTICAL Journal of Analytical Atomic Spectrometry Pub Date : 2026-02-12 DOI:10.1039/D5JA00451A
Munkhbat Batsaikhan, Hironori Ohba, Takahiro Karino, Katsuaki Akaoka, Ikuo Wakaida, Yoshihiro Iwata and Kan Sakamoto
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Abstract

This study presents the development and application of a fiber-optic laser-induced breakdown spectroscopy (FO-LIBS) system designed for remote, in situ analysis of nuclear fuel debris at the Fukushima Daiichi Nuclear Power Station (FDNPS). To evaluate its performance in uranium detection and spatial mapping, a two-stage experimental approach was used. In the first stage, the FO-LIBS detection limit for uranium was determined in a laboratory environment using UO2 samples with different concentrations. Based on prominent uranium emission lines and calibration restricted to a low-concentration linear region (<10 wt%), a detection limit of approximately 3.5–3.7 wt% was achieved, with regression coefficient R2 = 0.95. The system's ability for two-dimensional elemental mapping was then demonstrated on a simulated debris sample (UO2–Zr–SUS), and the LIBS spatial maps were validated against scanning electron microscopy-energy dispersive X-ray spectroscopy measurements. In the second stage, the FO-LIBS system was deployed for the first time in a hot cell under high radiation (230 mSv h−1) to analyse an actual boiling water reactor's spent fuel sample, as an exemplar of FDNPS fuel debris. The system successfully identified the main fuel components (U and Zr) along with several long-lived fission products and related markers (analytical proxies) such as Sr, Cs, Mo, Ba, and Rb. The LIBS emission intensity of Ba, Rb, and Cs near the periphery region was slightly higher than at the center of the fuel. This indicates a higher concentration of these elements in that area.

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用光纤激光诱导击穿光谱法测量乏燃料样品中的铀和裂变产物
本研究介绍了一种光纤激光诱导击穿光谱(FO-LIBS)系统的开发和应用,该系统设计用于福岛第一核电站(FDNPS)核燃料碎片的远程原位分析。为了评估其在铀探测和空间测绘中的性能,采用了两阶段的实验方法。在第一阶段,利用不同浓度的UO2样品在实验室环境下确定了FO-LIBS对铀的检出限。基于突出的铀发射线和校准限制在低浓度线性区域(<10 wt%),检测限约为3.5-3.7 wt%,回归系数R2 = 0.95。然后在模拟碎片样品(UO2-Zr-SUS)上验证了该系统二维元素映射的能力,并通过扫描电子显微镜-能量色散x射线光谱测量验证了LIBS空间地图。在第二阶段,FO-LIBS系统首次部署在高辐射(230 mSv h−1)的热池中,以分析实际沸水反应堆的乏燃料样品,作为FDNPS燃料碎片的范例。该系统成功地识别了主要的燃料成分(U和Zr),以及一些长寿命的裂变产物和相关的标记物(分析代理),如Sr, Cs, Mo, Ba和Rb。Ba、Rb、Cs的LIBS排放强度在燃料外围区域略高于燃料中心区域。这表明这些元素在该区域的浓度较高。
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来源期刊
CiteScore
6.20
自引率
26.50%
发文量
228
审稿时长
1.7 months
期刊介绍: Innovative research on the fundamental theory and application of spectrometric techniques.
期刊最新文献
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