Maman Kartaman Ajiriyanto
Pusat Teknologi Bahan Bakar Nuklir – BATAN

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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.
INTERAKSI BAHAN BAKAR U3Si2-Al DENGAN KELONGSONG AlMg2 PADA ELEMEN BAKAR SILISIDA TMU 2,96 gU/cm3 PASCA IRADIASI Aslina Br. Ginting; Maman Kartaman Ajiriyanto; Supardjo Supardjo
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 21 No. 1 (2015): 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.2015.21.1.2255

Abstract

INTERACTION OF U3Si2-Al FUEL ELEMENT WITH AlMg2 CLADDING ON POST IRRADIATION WITH LOADING OF URANIUM 2.96 gU/cm3. Interaction of U3Si2-Al fuel element with AlMg2 cladding on post irradiation of 2.96 gU/cm3 loading of uranium (TMU) of U3Si2-Al fuel elements plate (PEB) has been analyzed. The purpose of this research is to study the changes of microstructure of nuclear fuel elements during iradiation in reactor core. Understanding on interaction of U3Si2-Al fuel meat with AlMg2 cladding onpre and post irradiation needed to study the influence of radiation on fuel elements plate. PEB U3Si2-Al with 2.96 gU/cm3 by size 10 × 10 mm were heated in DTA (Differential Thermal Analysis) furnace with temperature variation at 450, 550, 650, 900 and 1350oC to perform pre irradiation test.Post irradiation samples were cut by size 2 × 10 mm as many as three samples taken from bottom, middle, and top of PEB in hotcell. The metallography preparation for each pieces of pre and post irradiation samples of U3Si2-Al fuel elements platewith 2.96 gU/cm3 weredone through steps mounting, grinding, polishing, and etching.Scanning Electron Microscope (SEM-EDS) were used to observe the pre irradiation microstructure of fuel elements U3Si2-Al with AlMg2 cladding interaction, while the post irradiationmicrostructure were observed by optical microscope in hot cell. The result show the interaction of U3Si2 with Al matrix or AlMg2 cladding in pre irradiation PEB U3Si2-Aloccurred agglomeration formed new compouds of U(Al,Si)x and UAlx formation. Agglomeration formation on heated pre irradiation samples were bigger while heating temperature increased. The post irradiation sampels shoed the oxide layer were formed outside the AlMg2 cladding and the inner side of caldding that contact to the fuel meat formedlight-grey U(Al,Si)xlayer at 1-3 micron of thickness.