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

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SIMULASI UJI TAK MERUSAK PELAT ELEMEN BAKAR PASCA IRADIASI MENGGUNAKAN METODE PENETRANT TEST Yusuf Gigih Wicaksono; Helmi Fauzi Rahmatullah; Refa Artika; Sri Ismarwanti; Rohmad Sigit
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.2022.28.3.6760

Abstract

The post-irradiation examination aims to determine the performance of nuclear fuel during irradiation in the reactor. Non-destructive tests at the Radiometallurgical Installation include visual observations, digital X-ray radiography, and ultrasonic tests for inspection of potential defects or anomalies in the fuel plate (PEB). Limitations in the detection of surface defects necessitate other nondestructive test methods, i.e., to simulate the use of the penetrant test method on the PEB dummy. The purpose of this simulation is to determine the ability of the penetrant test method to complement the non-destructive test data that has been previously conducted as well as to review the capability of the hot cell in applying the method. The simulation was carried out using a dummy PEB with artificial defects and used water-washable visible penetrant and solvent-removable visible penetrant. The simulation stages for implementing the penetrant test include precleaning, applying the penetrant, dwell time, removing the penetrant, applying developer, inspection, and post-cleaning. The simulation results with the penetrant test method are able to detect surface defects in the form of cracks and porosity, but cannot detect blister defects. Based on the simulation results, it can be concluded that the penetrant test can be an alternative method to complement the non-destructive test using X-ray and ultrasonic radiographic methods. In addition, to accommodate the application of the penetrant test method in IRM hot cells, it is necessary to develop support facilities while still paying attention to ease of handling and safety systems. 
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.
ANALISA DAN INTERPRETASI DATA HASIL UJI TAK MERUSAK DALAM RANGKA PENGEMBANGAN BASIS DATA POTENSI CACAT PADA PELET UO2 Refa Artika; Helmi Fauzi Rahmatullah; Yusuf Gigih Wicaksono; Sri Ismarwanti; Rohmad Sigit
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 29 No. 2 (2023): 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.2023.29.2.7001

Abstract

The development of nuclear fuel for both research and power reactors has been the focus of Research Center for Nuclear Fuel Cycle and Radioactive Waste Technology (PRTDBBNLR) research from fabrication, pre-irradiation, irradiation, and post-irradiation examination phases. As the only post-irradiation examination facility in Southeast Asia, Radiometallurgy Installation (IRM) is required to be ready to evaluate the performance of nuclear fuel, one of them is the short pin PWR-fuel containing UO2 pellets which is currently in the irradiation process. One of the efforts made by IRM is to develop non-destructive testing techniques, including methods, analysis, interpretation, and inventory of potential defects that may occur systematically in short pin PWR-fuel containing UO2 pellets. The aim of this research is to inventory methods and data of potential defects in UO2 pellets for a post-irradiation examination database. Characterization was performed on five samples of pre-irradiated UO2 pellets with variations in sintered/raw, good/defect conditions, and differences in uranium enrichment (3%, 4%, and 5%) using visual test methods and digital X-ray radiography. Visual examination can provide interpretation results regarding the conditions on the surface of the UO2 pellets. Digital X-ray radiography was operated at a voltage of 150 kV and a current of 1800 µA to produce a digital image then be carried out an image enhancement process using an image processor to interpret the UO2 pellets. Digital X-ray radiography method and image enhancement process adds information of UO2 pellets data. Cracks and surface holes of UO2 pellets can be mapped. The difference in uranium enrichment can be observed from the gray value graphic. Information from this interpretation will be useful as an initial database of interpretation methods to determine the condition of the UO2 pellets in the irradiated short pin PWR-fuel.
Co-Authors Aslina Br. Ginting Helmi Fauzi Rahmatullah Rohmad Sigit Sri Ismarwanti Supardjo Yusuf Gigih Wicaksono