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All Journal Eksplorium : Buletin Pusat Pengembangan Bahan Galian Nuklir Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir
Triyono Basuki
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Chemical Engineering, Chemistry & Bioengineering Earth & Planetary Sciences Energy Engineering Materials Science & Nanotechnology

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Preliminary Study of Yttrium Extraction from Tin Slag Using Hydrochloric Acid Rachmat Fauzi Hidayat; Kurnia Trinopiawan; Mohammad Zaki Mubarok; Rommy Rommy; Riesna Prassanti; Aditya Widian Putra; Amalia Ekaputri Hidayat; Kurnia Setiawan Widana; Tri Purwanti; Roza Indra Laksmana; Triyono Basuki; Afiq Azfar Pratama; Suci Indryati
EKSPLORIUM Vol. 46 No. 2 (2025): NOVEMBER 2025
Publisher : BRIN Publishing

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/eksplorium.2025.13299

Abstract

Tin slag, a byproduct of tin smelting, comprises several important metals, including yttrium, tantalum, manganese, iron, aluminum, titanium, and others. As an element that is used a lot in advanced materials, the separation of Yttrium becomes one of the most important steps in rare earth elements extraction. By using the alkali fusion process and leaching method, yttrium in the tin slag has been successfully extracted. The tin slag was subjected to an alkali fusion treatment with sodium hydroxide at a temperature of 700 °C, and the frit was ground into several particle sizes of +100 to -325 mesh using a laboratory ball mill and mortar. The frit was then leached using hydrochloric acid, with four parameters used: temperature, acid concentration, particle size, and stirring speed. The extracted yttrium reached a percentage of up to 86.94% at a temperature of 80 °C, acid concentration of 2 M, particle size of -325 mesh, and stirring speed of 150 rpm.
OPTIMASI PEMISAHAN SESIUM DI DALAM PELAT ELEMEN BAKAR TIPE U3Si2/Al PASCA IRADIASI MENGGUNAKAN METODE PENGENDAPAN KLOROPLATINAT Arif Nugroho; Komar Sutriah; Sri Mulijani; Triyono Basuki; Ahmad Ade Rofiqi; Noviarty; Helmi Fauzi Rahmatullah; Ganisa Kurniati Suryaman; Guswardani
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 30 No. 1 (2024): Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir
Publisher : Badan Riset dan Inovasi Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/urania.2024.8679

Abstract

Several methods for separating fission product ¹³⁷Cs from uranium isotopes (²³⁸U, ²³⁵U, ²³⁶U, and ²³⁴U) in U₃Si₂/Al fuel have been widely developed. Optimization and separation were performed using the chloroplatinate precipitation to establish a new cesium (Cs) separation method. The method developed in this research offers the potential to achieve higher-purity cesium precipitates. This study aims to develop a method of separating the ¹³⁷Cs isotope from U₃Si₂/Al fuel element plates (PEB) using chloroplatinate reagents. The procedure involves dissolving the pre-irradiation U₃Si₂/Al PEB and adding several elements such as Sm, Sr, Cs, and Nd to represent the composition of pre-irradiation PEB, simulating its original condition. The cesium precipitation process in the supernatant solution was carried out by adding HCl and NaOH to separate impurities from cesium. The precipitation was conducted by adding H₂PtCl₆ to precipitate and isolate cesium from other elements. The precipitation process was optimized by varying the temperature and precipitation time. The optimum precipitation conditions were achieved at a temperature of -3°C and a time of 10 minutes, resulting in a Cs2PtCl6 precipitate weighing 0.3361 g. XRD and SEM analyses were used to complement and verify the cesium separation results using the chloroplatinate precipitation method, showing a uniform distribution of all elements. The purity of the Cs2PtCl6 precipitate obtained was 100%, with a diffractogram pattern identical to the reference.
ANALISIS RADIONUKLIDA 137Cs DI DALAM PELAT ELEMEN BAKAR NUKLIR U3Si2/Al DENSITAS 4,8 gU/cm3 BURN UP 60% PASCA IRADIASI MENGGUNAKAN METODE KLOROPLATINAT Arif Nugroho; Komar Sutriah; Sri Mulijani; Triyono Basuki; Ahmad Ade Rofiqi; Boybul; Erlina Noerpitasari; Rosika Kriswarini; Juan Carlos Sihotang; Agus Jamaludin
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 30 No. 2 (2024): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir
Publisher : Badan Riset dan Inovasi Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/urania.2024.9142

Abstract

Analysis of 137C isotopes in post-irradiation nuclear fuel is vital in determining burn up and fuel behavior during fission. The 137Cs isotope is used as input data for burn up calculations because it has a long half-life (30.17 years) and a large fission yield (6.026%). This study uses the chloroplatinate precipitation method to separate the 137Cs isotope from U3Si2/Al nuclear fuel with a density of 4.8 gU/cm³ with a burn up of 60% after irradiation. The separation process begins with cutting and dissolving the fuel sample, followed by the addition of CsNO₃ as a carrier solution and H₂PtCl₆ reagent to form Cs₂PtCl₆ precipitate. The results of the analysis using gamma spectrometry showed that the spectrum of the Cs₂PtCl₆ precipitate had the highest peak area of ​​67.6298 cps compared to the brown residue of 0.9165 cps and the supernatant of 0.2450 ​​cps. In addition, the results of this study showed an increase in the separation recovery value from 70% to 96.39%, which indicates the success of the separation of the 137Cs isotope from the U3Si2/Al fuel solution with a density of 4.8 gU/cm3 using the chloropaltinate precipitation method. The results of elemental mapping of the Cs₂PtCl₆ precipitate using SEM (scanning electron microscope) showed an even distribution of platinum (Pt), cesium (Cs), and chlorine (Cl) components, which shows the efficiency of this precipitation method. In addition, EDS (energy dispersive X-ray spectroscopy) analysis shows the elemental composition of the Cs₂PtCl₆ deposits. The three main elements identified are Pt, Cl, and Cs. The results of this study can provide an essential contribution to evaluating the performance of U3Si2/Al fuel with a density of 4.8 gU/cm3 after irradiation. They can be used for further research on Cs isotopes.
Co-Authors Aditya Widian Putra Afiq Azfar Pratama Agus Jamaludin Ahmad Ade Rofiqi Amalia Ekaputri Hidayat ARIF NUGROHO Boybul Erlina Noerpitasari Ganisa Kurniati Suryaman Guswardani Helmi Fauzi Rahmatullah Juan Carlos Sihotang Komar Sutriah Kurnia Setiawan Widana Kurnia Trinopiawan Mohammad Zaki Mubarok Noviarty Rachmat Fauzi Hidayat Riesna Prassanti Rommy Rommy Rosika Kriswarini Roza Indra Laksmana Sri Mulijani Suci Indryati Tri Purwanti