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All Journal Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir
Supardjo
National Research and Innovation Agency

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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.
STUDY OF FISSION GAS BUBBLES AND INTERACTION LAYER ON IRRADIATED U3Si2-Al DENSITY OF 4.8 gU/cm3 Juan Carlos Sihotang; Maman Kartaman Ajiriyanto; Anditania Sari Dwi Putri; Ely Nurlaily; Junaedi; Aslina Br Ginting; Supardjo
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 28 No. 2 (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.2022.28.2.6670

Abstract

Uranium-silicide compound fuel dispersed in aluminium matrix (U3Si2-Al) have been used in a large number of research reactors around the world because of its excellent behavior under irradiation. This fuel also provides high uranium density with typical fuel loading up to 4.8 gU/cm3 to compensate for the reduced fissile amount in LEU. To improve the density of current U3Si2-Al (2.96 gU/cm3) used in Indonesian GA Siwabessy Multipurpose Research Reactor, U3Si2-Al dispersion fuel plate with density of 4.8 gU/cm3 (U235 ∼19.75%) had been irradiated in RSG GAS for 175 days at 15 MW power to burnup level of approximately 40%. The characterization was performed using SEM-EDS and optical microscope to study microstructure of the irradiatted fuel, largely the fission gas bubbles and the interaction layer between U3Si2 fuel and Al matrix. The average diameter of the bubbles with diameter from 0.06 to 0.55 μm was 0.21 μm. The interaction layer was identified as U(Al,Si)2,3 with thickness of approximately 1.5 μm. The relatively small fission gas bubbles and the interaction layer didn’t cause swelling on the fuel and the overall performance of the fuel plate was very good.
Co-Authors Anditania Sari Dwi Putri Aslina Br Ginting Aslina Br. Ginting Boybul Ely Nurlaily Helmi Fauzi Rahmatullah Juan Carlos Sihotang Junaedi Maman Kartaman Ajiriyanto Refa Artika Rohmad Sigit Sri Ismarwanti Sungkono Yanlinastuti