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All Journal Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir
Noviarty
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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.
Co-Authors Ahmad Ade Rofiqi Andon Insani ARIF NUGROHO Enung Nurlia Ganisa Kurniati Suryaman Guswardani Helmi Fauzi Rahmatullah Komar Sutriah Mohammad Khotib Rosika Kriswarini Sri Mulijani Triyono Basuki