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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 Junaedi; Aslina Br Ginting; Supardjo Supardjo
Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol 28, No 2 (2022): JUNI, 2022
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Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/urania.2022.28.2.6670

Abstract

STUDY OF FISSION GAS BUBBLES AND INTERACTION LAYER ON IRRADIATED U3Si2-Al DENSITY OF 4.8 gU/cm3. 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.Keyword:  LEU, uranium-silicide, post-irradiation examination, interaction layer, fission gas bubbles.
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 Supardjo
Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol 28, No 3 (2022): OKTOBER, 2022
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Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/urania.2022.28.3.6786

Abstract

UJI PASCA IRADIASI PELAT ELEMEN BAKAR U3Si2/Al DENSITAS 4,8 gU/cm3 PADA BURNUP 60%: PENGAMATAN VISUAL, RADIOGRAFI SINAR-X DAN ANALISIS CITRA. Pengembangan bahan bakar U3Si2/Al densitas tinggi telah dilakukan melalui peningkatan densitas bahan bakar nuklir dari 2,96 gU/cm3 menjadi 4,8 gU/cm3. Peningkatan densitas uranium memiliki dampak terhadap integritas mekanik kelongsong dan stabilitas geometri, sehingga diperlukan pengujian pascairadiasi. Pengujian pascairadiasi yang dilakukan meliputi pengamatan visual, uji radiografi sinar-X dan analisis citra pada Pelat Elemen Bakar (PEB). Pengamatan visual sepanjang permukaan PEB dilakukan menggunakan periskop yang terdedikasi di operating area hot cell 102 dan didokumentasikan dengan bantuan kamera melalui jendela hot cell. Pengujian radiografi sinar-X dilakukan pada tegangan 150 kV dan kuat arus 1500 µA. Citra yang dihasilkan dianalisis lebih lanjut menggunakan software ImageJ. Pengamatan visual tidak menemukan indikasi cacat permukaan, lapisan oksida yang berlebih, swelling, blister, maupun cacat permukaan lainnya. Interpretasi citra radiografi sinar-X menunjukkan profil bahan bakar yang homogen, tidak menemukan indikasi cacat sub-permukaan, serta menghasilkan profil burn up yang sesuai dengan hasil pengujian gamma scanning. Berdasarkan hasil pengujian tak merusak, secara keseluruhan PEB U3Si2/Al densitas 4,8 gU/cm3 selama iradiasi di teras RSG-GAS menunjukkan kinerja yang cukup baik.Kata kunci: Uji pascairadiasi, PEB U3Si2/Al, pengamatan visual, radiografi sinar-X, analisis citra
Co-Authors Anditania Sari Dwi Putri Aslina Br Ginting Aslina Br. Ginting Ely Nurlaily Helmi Fauzi Rahmatullah Juan Carlos Sihotang Junaedi Junaedi Maman Kartaman Ajiriyanto Refa Artika Rohmad Sigit Sri Ismarwanti