Refa Artika
Pusat Teknologi Bahan Bakar Nuklir – BATAN

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UJI TAK MERUSAK PELAT ELEMEN BAKAR U3SI2/Al DENSITAS URANIUM 4,8 gU/cm3 MENGGUNAKAN RADIOGRAFI SINAR-X DIGITAL Refa Artika; Rohmad Sigit; Helmi Fauzi Rahmatullah; Supardjo Supardjo; Aslina Br. Ginting
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 26 No. 1 (2020): 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.2020.26.1.5822

Abstract

NON DESTRUCTIVE TEST FOR U3Si2/Al FUEL PLATE WITH 4,8 gU/cm3 URANIUM DENSITY USING DIGITAL X-RAY RADIOGRAPHY. Non-destructive test for irradiated U3Si2/Al fuel plate with 4,8 gU/cm3 uranium density and 20, 40, and 60% burn-up has been done. The test includes visual inspection, radiographic image analysis, and dimension measurement using digital x-ray radiography. The non-destructive test aimed to determine the performance, integrity, and reliability of U3Si2/Al fuel plate with 4,8 gU/cm3 uranium density during irradiation at RSG-GAS. Reliability and safety of the fuel during irradiation are indicated by the absence of anomalies in the post-irradiation examination result. Three samples of irradiated U3Si2/Al fuel element (FE) with 20, 40, and 60 % burn-up were transferred from RSG-GAS to RMI hot cell 101 through transfer channel of Interim Storage Spent Fuel (ISSF). The U3Si2/Al fuel plate were then transferred to hot cell 103 for non-destructive test using digital x-ray radiography with seven shots for good resolution radiographic images. The radiographic images were evaluated to obtain data of defects and dimensions such as meat width, fuel plate width, meat-cladding distance, right-left meat- cladding boundary distance at the far side (SJ) and the near side (SD). The X-ray radiography analysis shows the presence of white spot in the middle of U3Si2/Al fuel cladding with 20% burn- up. Meanwhile, indication of surface defects and other defects were not found for the 40 and 60% burn-up samples. The dimensional measurement data show no dimensional changes, which indicates solid integrity after irradiation in the RSG-GAS. The measurement data analisis can further be used for mapping the sampling spots for the next test.
UJI TAK MERUSAK SHORT PIN PWR – FUEL DUMMY PASCA IRADIASI Rohmad Sigit; Refa Artika; Maman Kartaman Ajiriyanto; Tri Yulianto
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 26 No. 2 (2020): 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.2020.26.2.6058

Abstract

NON-DESTRUCTIVE TEST OF IRRADIATED SHORT PIN OF PWR TYPE – FUEL DUMMY. Post- irradiation examination (PIE) for nuclear fuel is used as an indicator of fuel performance reliability during the irradiation process. The Center for Nuclear Fuel Technology (PTBBN) conducts research and development of nuclear fuel for Pressurized Water Reactor (PWR). Short pin of PWR fuel dummy with zircaloy-4 cladding has been irradiated at the Multipurpose Reactor – G.A. Siwabessy (RSG-GAS) and has been sent to the Radiometallurgy Installation (IRM) – PTBBN. Non-destructive tests conducted at the IRM includes visual observation and X-ray radiographic test. Visual observations using a digital camera were done in hot cell 102, while X-ray radiographic test was carried out in hot cell 103 IRM. X-ray radiographic test using the voltage and current parameters at a range of 120-125 kV and 1000-1100 uA. The test material was placed at a height of 60 cm from the detector to obtain a 100% magnification. Visual observation shows the formation of several spots indicating oxidation on the short pin PWR fuel dummy surface. Radiographic images from X- ray radiographic testing do not show any anomalies, which is indicated by relatively homogeneous gray value in the axial and radial directions. Generally, based on the non-destructive test results, performance of the short pin PWR - fuel dummy is relatively satisfactory with no significant defects. To confirm the existence of oxides formation on the surface of the short pin PWR fuel dummy, Eddy Current test is needed, followed by microstructure observations.