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All Journal Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir
Juan Carlos Sihotang
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MODEL SIMULATION OF THE EFFECT OF ZINC PHOSPHATE INHIBITOR ON CORROSION RATE OF SECONDARY COOLING PIPE FOR PRESSURIZED WATER REACTOR USING PREDICTOR-CORRECTOR METHOD Fajar Al Afghani; Maman Kartaman Ajiriyanto; Rosika Kriswarini; Arif Nugroho; Juan Carlos Sihotang; Ely Nurlaily; Anditania Sari Dwi Putri
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.2024.8677

Abstract

Corrosion is one of the unavoidable problems in nuclear reactor cooling systems. Secondary Cooling Pipe Multi-Purpose Reactor G.A Siwabessy (MPR-GAS) based on low carbon steel is very easy to oxidize because it is an open circulation cooling system. Zinc-phosphate inhibitor (ZnPO4) is one of the inhibitors used to inhibit the corrosion reaction that occurs between the low carbon steel cooling pipe and the cooling water environment. The research has been carried out on numerical calculations to find a solution for the corrosion rate model of steel with and without an inhibitor by the Predictor-corrector method. The simulation results show that the effect of ZnPO4 inhibitor on the corrosion rate of steel is seen as a relationship between inhibitor concentration and stable time, if the inhibitor concentration increases, the stable time will also increase. The rate of corrosion that occurs (reducing the concentration of corroded product). Therefore, the recommended inhibitor concentration value is 0.9% for models in 0.1 M HCL medium. This concentration is the most appropriate concentration to slow down the corrosion rate most minimal.
PENGUKURAN BERAT RADIONUKLIDA 137Cs DALAM LARUTAN PELAT ELEMEN BAKAR U3Si2/Al DENSITAS 4,8 gU/cm3 PASCA IRADIASI DENGAN METODE KOLOM KROMATOGRAFI Boybul; Yanlinastuti; Erlina Noerpitasari; Juan Carlos Sihotang; Helmi Fauzi Rahmatullah; Arif Nugroho; Mohammad Sukron Fajrin Husein; Rohmad Sigit; Aslina Br Ginting; Susilo WIdodo
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.2024.8678

Abstract

The burn up value of the fuel is one of the parameters that must be known in the post-irradiation examination. The determination of burn up aims to determine the performance of U3Si2/Al fuel after being used in the reactor. One of the isotops that can be used as an indicator of burn up is 137Cs because it has a long half-life (T1/2) of 30.17 years with a fission yield of 6.26%. Therefore, in this study, a separation was carried out to determine the amount of 137Cs in the U3Si2/Al fuel solution post irradiation using the cation exchange column method using zeolit from Lampung along with its recovery rate. The solution of irradiated U3Si2/Al fuel from Top (T), Middle (M), and Bottom (B) position, was each pipetted in a duplicate manner (duplo) in an amount of 50 µL and added with 2 mL of 0.1 M HNO3. The solutions were then measured activity using a gamma spectrometer to obtain the initial weight of 137Cs radionuclide. The solution was then inserted into a chromatography column containing 700 mg of zeolit Lampung and allowed to flow under vacuum condition. The separation results showed that 137Cs was bound to the zeolit in the form of 137Cs-zeolit solid phase, while other isotops remained in the liquid phase. The solid 137Cs-zeolit and 137Cs in the supernatant were then measured with a gamma spectrometer to determine the weight of 137Cs bound to the zeolit. The measurement results showed that the average initial weight of 137Cs (before separation) were 7.49 × 10-3 µg/gFEP and dan 6.97 × 10-3 µg/gFEP for T1 and T2 from top section, 10.50 × 10-3 µg/gFEP for M1 from Middle section, and dan 8.43 × 10-3 µg/gFEP and 8.76 × 10-3 µg/gFEP for B1 and B2 from Bottom section, respectively. After separation, the average weight of 137Cs were 7.43 × 10-3 µg/gFEP and 6.82 × 10-3 µg/gFEP for T1 and T2, 10.10 × 10-3 µg/gFEP for M1, and 8.32 × 10-3 µg/gFEP and 8.41 × 10-3 µg/gFEP for B1 and B2, respectively. From the weight of 137Cs before and after separation, the average separation recovery with the cation exchange chromatography column method using zeolit was obtained at 97.748%. This recovery value indicates that zeolit Lampung is highly selective for absorbing 137Cs in the solution of irradiated U3Si2/Al fuel.
IMPROVEMENT OF PLASMA ELECTROLYTIC OXIDATION (PEO) COATING ON ZIRCONIUM ALLOYS USING ADDITIVES FOR NUCLEAR FUEL CLADDING APPLICATION Juan Carlos Sihotang; Maman Kartaman Ajiriyanto; Anawati
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.2024.9141

Abstract

This study explores the improvement of Plasma Electrolytic Oxidation (PEO) coatings on zirconium alloys using additives for pressured water reactor (PWR) fuel cladding application. PEO is a promising surface treatment for zirconium alloys, offering improved corrosion and wear resistance, essential for applications in extreme environments, such as nuclear reactors. Various types of stable particle and dissolved additives were incorporated into the electrolyte during PEO process to modify the coating's microstructure, phase composition, and mechanical properties. The incorporation of stable particle such as Al₂O₃, CeO₂, and Y₂O₃ not only reduces surface porosity and roughness but also increases the presence of the tetragonal zirconia phase (t-ZrO₂), leading to enhanced corrosion and wear resistance. Additionally, the use of dissolved additives, including complex agents and salts, positively affected plasma characteristics and further improved coating density and durability.
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 Anawati Anditania Sari Dwi Putri Andon Insani ARIF NUGROHO Aslina Br Ginting Boybul Ely Nurlaily Erlina Noerpitasari Fajar Al Afghani Helmi Fauzi Rahmatullah Komar Sutriah Maman Kartaman Ajiriyanto Mohammad Khotib Mohammad Sukron Fajrin Husein Rohmad Sigit Rosika Kriswarini Sri Mulijani Susilo WIdodo Triyono Basuki Yanlinastuti