Evaluation of bentonite–graphite (B–G) mixture homogeneity using visible-near infrared spectroscopy and its impact on B–G buffer block manufacturability

The homogeneity of bentonite-graphite (B-G) mixtures is essential for the performance of engineered barrier systems in high-level radioactive waste (HLW) repositories. Uniform graphite distribution enhances thermal conductivity while maintaining the protective functions of bentonite. This study investigates the feasibility of using visible and near-infrared (VIS-NIR) spectroscopy combined with partial least squares regression (PLSR) to assess B-G mixture homogeneity. Small-quantity mixtures containing 0-5 wt% graphite were prepared, and hyperspectral data (400-1,000 nm) were collected. A PLSR model was developed to predict graphite content from the spectral data, achieving high accuracy (R² = 0.992, RMSE = 0.151 wt%) using five latent variables. The model was applied to large-scale mixtures blended using a double helix screw mixer. Samples collected at different time intervals were evaluated to determine the required mixing time for achieving homogeneity. After 120 min of mixing, statistical tests confirmed uniform graphite distribution. Buffer blocks were then fabricated using both homogeneous and inhomogeneous mixtures. Blocks from homogeneous mixtures showed no visible defects, whereas those from inhomogeneous mixtures exhibited edge spalling and lateral cracking. These results demonstrate that VIS-NIR spectroscopy with PLSR is a reliable, nondestructive method for evaluating mixture homogeneity and offers practical advantages for quality control in HLW buffer material production.

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Publication Details

Journal
Scientific Reports
Published
2026-01-14
DOI
https://doi.org/10.1038/s41598-025-34636-6
Primary Topic
Graphite, nuclear technology, radiation studies
Type
article
Field-Weighted Citation Impact
0.00

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article

Evaluation of bentonite–graphite (B–G) mixture homogeneity using visible-near infrared spectroscopy and its impact on B–G buffer block manufacturability

Gi-Jun Lee, Deuk-Hwan Lee, Seok Yoon, Hwan-Hui Lim
Scientific Reports
Graphite, nuclear technology, radiation studies
article

Evaluation of bentonite–graphite (B–G) mixture homogeneity using visible-near infrared spectroscopy and its impact on B–G buffer block manufacturability

Gi-Jun Lee, Deuk-Hwan Lee, Seok Yoon, Hwan-Hui Lim
article en

Abstract

The homogeneity of bentonite-graphite (B-G) mixtures is essential for the performance of engineered barrier systems in high-level radioactive waste (HLW) repositories. Uniform graphite distribution enhances thermal conductivity while maintaining the protective functions of bentonite. This study investigates the feasibility of using visible and near-infrared (VIS-NIR) spectroscopy combined with partial least squares regression (PLSR) to assess B-G mixture homogeneity. Small-quantity mixtures containing 0-5 wt% graphite were prepared, and hyperspectral data (400-1,000 nm) were collected. A PLSR model was developed to predict graphite content from the spectral data, achieving high accuracy (R² = 0.992, RMSE = 0.151 wt%) using five latent variables. The model was applied to large-scale mixtures blended using a double helix screw mixer. Samples collected at different time intervals were evaluated to determine the required mixing time for achieving homogeneity. After 120 min of mixing, statistical tests confirmed uniform graphite distribution. Buffer blocks were then fabricated using both homogeneous and inhomogeneous mixtures. Blocks from homogeneous mixtures showed no visible defects, whereas those from inhomogeneous mixtures exhibited edge spalling and lateral cracking. These results demonstrate that VIS-NIR spectroscopy with PLSR is a reliable, nondestructive method for evaluating mixture homogeneity and offers practical advantages for quality control in HLW buffer material production.

Scientific ReportsVol. 16(1)
Korea Atomic Energy Research Institute (KR), Korea Institute of Nuclear Safety (KR), Korea Institute of Civil Engineering and Building Technology (KR)
Institute for Korea Spent Nuclear Fuel, National Research Foundation, National Research Foundation of Korea, Ministry of Science and ICT, South Korea
Openalex Percentile: Top 88%
Graphite, nuclear technology, radiation studies
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