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Pamungkas, N. S.
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Atmospheric Nitrogen Plasma-Induced for Embedding NH2@Cubic-Bicontinuous Mesoporous Silica as Uranium (VI) Adsorbent Candidate in Seawater Pamungkas, N. S.; Wongsawaeng, D.; Swantomo, D.; Kamonsuangkasem, K.; Chio-Srichan, S.
Atom Indonesia Vol 50, No 2 (2024): AUGUST 2024
Publisher : National Research and Innovation Agency

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/aij.2024.1301

Abstract

This work aims to achieve interesting progress in uranium extraction by introducing a promising strategy that utilizes atmospheric nitrogen plasma-induced amine modification of CBC (Cubic Bi-continuous) material, providing a compelling pathway to enhance CBC's adsorption properties specifically for uranium harvesting. CBCs mesoporous silica samples were prepared by mixing the Pluronic F-127 as a template and TEOS (Tetraethyl Orthosilicate) as silica sources in the sol-gel process under acidic conditions. The obtained CBCs were treated using nitrogen plasma at room temperature (RT) under atmospheric pressure in a customized-borosilicate plasma reactor. Subsequently, the treated CBSs were grafted with amine groups. The final samples were characterized using SAXS (Small Angle Synchrotron X-ray Scattering) to determine the phase and structure, SEM-EDS (Scanning Electron Microscopy-Energy Dispersive Spectroscopy) analysis to quantify the presence of silica, oxygen, and embedded nitrogen, and Specific Surface Area (SSA) Analyzer using Brunauer-Emmett-Teller (BET) method to determine the specific surface area and pore size distribution. The SAXS profiles indicate that the obtained samples can be classified as CBCs Im3m mesoporous silica. The presence of silica, oxygen, and nitrogen was verified through SEM-EDS analysis, with approximate compositions of 36-37 %, 51-62 %, and 0.7-1.0 %, respectively. The use of SSA analysis further supported the findings, confirming the typical adsorption isotherm IV model. The specific surface areas were measured to be 371 m2/g for pure CBC, 573 m2/g for P1-CBC, and 607 m2/g for P2-CBC. The pore size distribution analysis revealed mesoporous characteristics within the material, with pore sizes ranging from 4 to 6.5 nm. On a batch laboratory scale, the material achieved the highest adsorption capacity of 15.68 mg-U(VI)/g-NH2@P1-CBC from natural seawater after 1 hour of contact time.
Characterization and Sorption Study of Cesium-137 by Bentonite from Santrijaya, Indonesia as an Engineering Barrier Material for Radioactive Waste Disposal Facilities Sriwahyuni, H.; Krisnandi, Y. K.; Basuki, T.; Setiawan, B.; Budianti, A.; Anggraini, Z.; Nurliati, G.; Pamungkas, N. S.
Atom Indonesia Vol 51, No 3 (2025): DECEMBER 2025
Publisher : National Research and Innovation Agency

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/aij.2025.1628

Abstract

Engineered barrier materials, such as bentonite, play a critical role for the safety of radioactive waste disposal systems by limiting radionuclide migration. This study aims to evaluate the mineralogical, chemical, and morphological characteristics of natural bentonite from Santrijaya, Tasikmalaya, Indonesia, and to investigate its Cs-137 sorption behavior, focusing on its potential as a candidate for engineered barrier materials. X-Ray Diffraction (XRD) and X-Ray Fluorescence (XRF) analyses showed that the bentonite predominantly consists of montmorillonite, with silica contributing about 80 percent of its composition. The material shows a specific surface area of 121.89 m²/g and a cation exchange capacity of 43.23 meq/100g, supporting its suitability for radionuclide sorption. The sorption capacity at equilibrium (q_e) achieved at 536.67 mg-Cesium/g-bentonite after 10 days of contact time, with adsorption kinetics that follows the Pseudo-Second Order (PSO) model and the distribution coefficient (K_d) value of 5211 mL/g. The study shows the competitive effects of K+ and Na+ ions, with K+ ions showing a stronger competitiveness for Cs-137 binding sites than that of Na+, which could influence radionuclide retention. These findings highlight the high sorption efficiency and stability of Santrijaya bentonite, showing its potential as a barrier material for radioactive waste containment systems and suggest the necessity of considering competing ion interactions in the design of barrier materials.