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All Journal Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir
Aslina Br. Ginting
National Research and Innovation Agency

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OXIDE LAYER CHARACTERIZATION OF AlMg2 CLADDING OF IRRADIATED U3Si2/Al FUEL WITH 4.8 gU/cm3 DENSITY Juan Carlos Sihotang; Maman Kartaman Ajiriyanto; Ely Nurlaily; Junaedi; Aslina Br. Ginting
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 28 No. 3 (2022): 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.2022.28.3.6755

Abstract

To investigate the performance of AlMg2 cladding in the U3Si2/Al dispersion fuel, oxide layer characterization of AlMg2 cladding of the irradiated U3Si2/Al fuel with 4.8 gU/cm3 density was conducted. The oxide layer on the surface of AlMg2 cladding is one of the changes that occur on the cladding after theU3Si2/Al fuel plate has been irradiated in the RSG-GAS reactor to a burn-up of ∼40%. The characterization and observation of the oxide layer was conducted using SEM (Scanning Electron Microscope) and Energy-dispersive X-ray spectroscopy (EDS). Samples with a size of 3x3 mm were taken from the middle of the fuel plate (middle position). After cutting, metallographic preparation includes mounting, grinding, polishing, and ultrasonic cleaning. SEM preparation was carried out by sputter coating using Au layer. The oxide layer on the AlMg2 cladding has a thickness of 10.3 μm with a uniformly distributed cracks along the oxide layer.
RADIONUKLIDA CESIUM SEBAGAI INDIKATOR PENENTUAN BURNUP BAHAN BAKAR U3Si2/Al SECARA MERUSAK Aslina Br. Ginting; Yanlinastuti; Boybul; Supardjo; Sungkono
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 28 No. 3 (2022): 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.2022.28.3.6711

Abstract

Determination of burn-up using a destructive method was carried out by separation of 137Cs in the irradiated U3Si2/Al fuel element plate (FEP) with a density of 4.8 gU/cm3. Determination of burn-up by the destructive method aims to study the suitability of the burn-up obtained by the non-destructive method or using the Origen Code software. FEP U3Si2/Al with CBBJ code 251 was cut in duplo at the top, middle and bottom with a weight of Top-1= 0.049 gFEP and Top-2=0.058 gFEP, Middle-1= 0.055 gFEP and Middle-2= 0.024 gFEP, and Bottom-1= 0.056 gFEP and Bottom-2=0.075gFEP. FEP samples were dissolved in acid to obtain a fuel solution containing fission products of 134Cs, 137Cs, 235U and other isotopes. The fuel solution was pipetted 1 mL and then transferred from the hot cell to R.135 to separate the 137Cs from 235U by a cation exchange method using zeolite from Lampung. The fuel solution was pipetted 100 μL and put into the vial in duplicate, then 1000 mg Lampung zeolite was added to the cation exchange process. The separation results were 137Cs in solid phase, while uranium and other isotopes in liquid phase. The amount of activity (Bq) of the 137Cs isotope was measured with a Spectrometer- and then used for burn-up calculation. The results of the calculation of the burn-up were 26.9714%; 55,1431%; and 37.8855% for the top, middle and bottom pieces, respectively, with an average burn-up by 40%. These values are not much different from the burn-up obtained by the non-destructive method using gamma scanning, i.e., 24.4%; 52.7% ; and 37.6% for top, middle and bottom positions with an average of 38.23% and a burn-up calculated using the Origen code, which is 40%. 
UJI PASCA IRADIASI PELAT ELEMEN BAKAR U3Si2/Al DENSITAS 4,8 gU/cm3 PADA BURNUP 60%: PENGAMATAN VISUAL, RADIOGRAFI SINAR-X DAN ANALISIS CITRA Rohmad Sigit; Refa Artika; Helmi Fauzi Rahmatullah; Sri Ismarwanti; Aslina Br. Ginting; Supardjo
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 28 No. 3 (2022): 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.2022.28.3.6786

Abstract

The development of high density U3Si2/Al fuels has been carried out by increasing the fuel density from 2.96 gU/cm3 to 4.8 gU/cm3. Increasing the density of uranium has an impact on the mechanical integrity of the cladding and its geometric stability, so a post-irradiation examination is required. The post-irradiation examination carried out included visual inspection, X-ray radiographic tests, and image analysis. Visual inspection of the fuel surface was performed using a dedicated periscope in the operating area of hot cell 102 and documented using a camera through the hot cell window. X-ray radiographic test using the voltage and current parameters at 150 kV and 1500 μA, respectively. The radiographic image is further analyzed using ImageJ software. Based on visual inspections, no blisters, swelling, excessive oxide layer, or other surface defects were found. The interpretation of X-ray radiographic images clearly shows a homogeneous fuel profile, no evidence of sub-surface defects, and a burn-up profile that matches the results of the gamma scanning test. Based on non-destructive post-irradiation examination, the overall performance of the PEB U3Si2/Al density of 4.8 gU/cm3 during irradiation on the RSG-GAS core was excellent.
PEMISAHAN DAN ANALISIS 137Cs DALAM LARUTAN ELEMEN BAKAR UJI U3Si2/Al DENSITAS 4,8 gU/cm3 DENGAN BURNUP 60% MENGGUNAKAN METODE PENUKAR KATION Yanlinastuti; Arif Nugroho; Aslina Br. Ginting; Noviarty; Boybul; Iis Haryati; Agus amaludin; Erlina Noerpitasari; Rosika Kriswarini
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 28 No. 3 (2022): 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.2022.28.3.6739

Abstract

Separation and analysis of cesium isotope in U3Si2/Al fuel with a density of 4.8 gU/cm3 and 60% burnup by cation exchange using Lampung zeolite and Dowex resin has been carried out. The purpose of this research was to determine the weight of 137Cs in the fuel. The U3Si2/Al fuel pieces by the Bottom (B), Middle (M) and Top (T) sections were dissolved in duplicate with 6 M HCl and 6 M HNO3 to obtain a U3Si2/Al fuel solution. The separation of 137Cs started with the measurement 50 μL of fuel solution in 2 mL of 0.1 M HNO3 with a gamma spectrometer to determine the initial weight of 137Cs. The solution was put into a column containing Lampung zeolite and then flowed at a speed of 0.3 mL/minute. The resulting 137Cs isotope was bound to the zeolite and effluent containing other fission isotopes. Dowex resin, Cs carrier, and HCl was added into fuel solution, then put into a column containing R-Cl- resin. The effluent that left the column was put back into the column containing the R-NH4+ resin. The 137Cs isotope that was bound to R-NH4+ resin was eluted using 1 M HCI, then the 137Cs isotope was measured using a gamma spectrometer. The results of the 137Cs isotope measurement shows the weight of each sample with code B1=0.1772 μg/g; B-2=0.1635 μg/g; M-1=0.1395 μg/g; T-1=0.1230 μg/g and T-2=0.1036 μg/g with a recovery of B-1=99.54%; B-2=98.98%; M-1=98.99%; T-1=99.38% and T-2=98.98%. Meanwhile, the average weight of the 137Cs isotope separated by Dowex resin was B-1=0.1575 μg/g; B-2=0.1470 μg/g; M-1=0.1263 μg/g; T-1=0.1140 μg/g and T-2=0.0952 μg/g with a recovery of B-1=94.80%; B-2=95.35%; M1=97.94%; T-1=98.15% and T-2=98.89%. It was concluded that the method for separating 137Cs isotopes in U3Si2/Al fuel solution by using Lampung zeolite and Dowex resin did not have a significant difference. Both methods can be used to separate 137Cs in nuclear fuel. This analysis is used to complement the data to calculate the burnup value.
Co-Authors Agus amaludin Arif Nugroho Boybul Ely Nurlaily Erlina Noerpitasari Helmi Fauzi Rahmatullah Iis Haryati Juan Carlos Sihotang Junaedi Maman Kartaman Ajiriyanto Noviarty Refa Artika Rohmad Sigit Rosika Kriswarini Sri Ismarwanti Sungkono Supardjo Yanlinastuti