Article Per Year (5 Year)
p-Index From 2021 - 2026
0.702
P-Index
This Author published in this journals
All Journal Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir
Komar Sutriah
Unknown Affiliation

Published : 4 Documents Claim Missing Document
Claim Missing Document
Check
Articles

Found 4 Documents
Search

 1 
PERILAKU KOROSI BAJA KARBON RENDAH PIPA PENDINGIN SEKUNDER REAKTOR DALAM INHIBITOR ZINK FOSFAT Rosika Kriswarini; Mohammad Khotib; Andon Insani; Komar Sutriah; Noviarty; Arif Nugroho; Enung Nurlia
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.2024.8675

Abstract

Carbon steel, one of the fuction in nuclear industry is used as a material for the cooling pipe structure of nuclear reactor operating systems. In use, the pipe is susceptible to corrosion due to contact with cooling water. Inhibitors of zinc phosphate solution derived from a mixture of zinc chloride and phosphoric acid with concentration variations of 25, 35, 50, 75 and 100 ppm in 0.1% NaCl are used as materials to study the effect of corrosion rates of carbon steel. Electrochemical methods are helpful for observing the corrosion behavior of carbon steel in zinc phosphate media. Methods include Open Circuit Potential (OCP) for 600 seconds, Electrochemical Impedance Spectroscopy (EIS) in the frequency range of 105 Hz to 0.01 Hz and Potentiodynamic Plot (PDP) in the voltage range of -1 Volt to 1 Volt using potentiostat. To support the results of corrosion tests, morphological observations were carried out using SEM, chemical composition of substrat using XRF and C/S Analyzer and zinc phosphate solution content using AAS, UV-Vis and FTIR. The results obtained show that at a concentration of 35 ppm, the corrosion rate gives a lower value than at other concentrations. The corrosion rate is 11.7 mpy
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.
FORMULASI INHIBITOR KOROSI BERBASIS ZINK–FOSFAT DAN MIKO–DEA PADA PIPA PENDINGIN SEKUNDER REAKTOR SERBA GUNA GERRIT AUGUSTINUS SIWABESSY Rosika Kriswarini; Andon Insani; Mohammad Khotib; Komar Sutriah; Arif Nugroho; Juan Carlos Sihotang; Ade Saputra
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.2024.9143

Abstract

The material for the secondary cooling pipes of RSG-GAS is low carbon steel. The pipes carry fluids that have the potential to cause corrosion. To reduce the corrosion rate, both inorganic and organic inhibitors are added. The inhibitors used are a mixture of zinc-phosphate as an inorganic inhibitor and miko-DEA as an organic inhibitor in a 0.1% NaCl medium. Zinc-phosphate inhibitors are tested at concentrations of 25, 35, and 50 ppm, and miko-DEA inhibitors at concentrations of 50, 75, and 100 ppm. To study the effects on corrosion rate and the corrosion behavior of carbon steel, electrochemical methods were employed, including Open Circuit Potential (OCP) for 600 seconds, Electrochemical Impedance Spectroscopy (EIS) over a frequency range from 105 Hz to 0.01 Hz, and Potentiodynamic Plot (PDP) over a voltage range from -1 Volt to 1 Volt using a potentiostat. To support the corrosion test results, surface morphology of the samples with and without inhibitors was observed using SEM, and compounds in the zinc-phosphate and Miko-DEA solutions were identified using FTIR. The optimal formulation that resulted in the lowest corrosion rate was a mixture of 50 ppm zinc-phosphate and 75 ppm miko-DEA in a 0.1% NaCl medium. The achieved corrosion rate was 10.57 mpy.
Co-Authors Ade Saputra Agus Jamaludin Ahmad Ade Rofiqi Andon Insani ARIF NUGROHO Boybul Enung Nurlia Erlina Noerpitasari Ganisa Kurniati Suryaman Guswardani Helmi Fauzi Rahmatullah Juan Carlos Sihotang Mohammad Khotib Noviarty Rosika Kriswarini Sri Mulijani Triyono Basuki