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PERCOBAAN PEMBUATAN PELAT ELEMEN BAKAR U-7Mo-xSi/Al DALAM UKURAN MINI Supardjo; Agoeng Kadarjono; Isfandi; Yatno Dwi Agus Susanto; Setia Permana; Guswardani
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 25 No. 3 (2019): 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.2019.25.3.5697

Abstract

The purpose of this study is to obtain the optimized process parameters in the fabrication of a U-7Mo-xSi/Al mini plate complying with the specifications. The process flow started with synthesizing U-7Mo-xSi alloys (x = 1%, 2%, and 3%) using depleted uranium and continued to preparing U-7Mo-xSi powder, U-7Mo-xSi/Al fuel core, and U-7Mo-xSi/Al fuel element plates. The quality of the product was determined by analyses/tests including tests of raw materials and products from each end of the process by the appropriate type of test which is commonly applied to the manufacturing process of plate type fuel. The quality of U-7Mo-xSi alloy ingots, U-7Mo-xSi powder, and U-7Mo-xSi/Al fuel core was satisfactorily good and in compliance with the specifications, indicating that the applied process parameters were appropriate. The obtained fuel element plates, however, have not satisfied the requirements especially the thickness of the cladding, where there are still several measurement points whose thickness is <0.25 mm. To obtain cladding thickness according to the required specifications, it is necessary to experiment with other rolling parameters or replacing the cladding material with material of higher hardness.
ANALISIS CACAT BLISTER PADA KELONGSONG BAHAN BAKAR U3Si2/Al MENGGUNAKAN ULTRASONIC TEST Muhammad Fauzi; Roziq Himawan; Helmi Fauzi Rahmatullah; Setia Permana; Antonio Gogo
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 23 No. 3 (2017): 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.2017.23.3.3629

Abstract

Fuel integrity is one of safety considerations during nuclear reactor operation. Any defect resulted after reactor operation should be avoided. Thus, in nuclear fuel development, post-irradiation examination is necessary to be performed to ensure fuel integrity. Non-destructive test using ultrasonic method is one of alternative methods to perform post-irradiation examination. The objective of this analysis is to detect blister defect in cladding of plate type nuclear fuel. In post irradiation examination (PIE) using ultrasonic method, the operation parameters are necessary to determine. In this experiment, this analysis method was conducted on U3Si2/Al fuel element cladding consisting of blister defect. Ultrasonic tests were done using two techniques, i. e. pulse-echo and through transmission techniques. The results were presented in A-scan display. The results show that the longitudinal wave speed in water used in the testing is 1545 m/s. The optimal distance between the probe and the specimen when using pulse-echo technique is 20 mm. The optimal distance between the two probes when using through transmission technique is 40 mm. Tests at blister area using pulse-echo technique caused output signal to decrease by 19 %FSH, while through transmission technique caused output signal to decrease by 80 %FSH. According to the results it can be concluded that ultrasonic test is effective to detect a blister defect in plate type nuclear fuel, and through transmission technique exhibited a clearer difference between normal area and blister area in fuel cladding when compared to pulse-echo technique.