Rosika Kriswarini
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PEMISAHAN DAN ANALISIS 137Cs DARI LARUTAN PELAT ELEMEN BAKAR U-7%Mo/Al Dian Anggraini; Noviarty Noviarty; Yanlinastuti Yanlinastuti; Aslina Br. Ginting; Rosika Kriswarini; Arif Nugroho; Boybul Boybul
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 22 No. 3 (2016): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir
Publisher : Badan Riset dan Inovasi Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/urania.2016.22.3.3183

Abstract

The aim of this research is to get a valid method of separating cesium from U-7Mo/Al fuel plate solution through determination of parameter of method (accuracy, precision, and recovery). Precipitation method and cation exchange method that are used refer to standard ASTM 690-000 and research result of U3Si2/Al. Parameter method determination has been done by using 150 μL sample (U-7%Mo/Al fuel plate solution, 50 μL of standard solution in 2 mL of HCl 0,1 N. The sample solution was undergone precipitation process by using HClO4 concentrated and 225 mg of CsNO3 as carrier in temperature 0oC for an hour, while exchange cation process was done by using 400 mg of resin zeolite Lampung. The analysis of 137Cs in CsClO4 and 137Cs - zeolite was done by gamma spectrometer. Determination of recovery method was done by comparing count value of 137Cs before and after separation process. Recovery of precipitation method was obtained 95.56 % with accuracy and precision measurement of 0.375 % and 1.875 % respectively, while recovery of cation exchange method obtained 26.73 %. To sum up, the results show that precipitation method better than exchange cation method for separation 137Cs from U-7Mo/Al fuel plate solution.
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
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.
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.