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All Journal Urania Jurnal Ilmiah Daur Bahan Bakar Nuklir Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir
Maman Kartaman Ajiriyanto
Pusat Teknologi Bahan Bakar Nuklir - BATAN
Materials Science & Nanotechnology

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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): Juni 2020
Publisher : website

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/urania.2020.26.2.6058

Abstract

UJI TAK MERUSAK SHORT PIN PWR – FUEL DUMMY PASCA IRADIASI. Pelaksanaan uji pasca iradiasi untuk bahan bakar nuklir digunakan sebagai indikator kehandalan unjuk kerja bahan bakar selama proses iradiasi. Salah satu tahapan awal pengujian pascairadiasi adalah pengujian tak merusak. Pusat Teknologi Bahan Bakar Nuklir (PTBBN) melakukan pengembangan bahan bakar reaktor daya tipe Pressurized Water Reactor (PWR). Short pin PWR fuel dummy dengan material kelongsong zircaloy­–4 telah melalui proses iradiasi di Reaktor Serba Guna – G.A. Siwabessy (RSG–GAS) dan telah dikirim ke hot cell Instalasi Radiometalurgi (IRM) – PTBBN. Pengujian tak merusak yang dilakukan di IRM antara lain melalui pengamatan visual dan pengujian radiografi sinar–X. Pengamatan visual dilakukan di hot cell 102 dengan bantuan kamera digital, sedangkan pengujian radiografi sinar–X dilakukan di hot cell 103 IRM. Pengujian radiografi sinar–X menggunakan parameter tegangan dengan interval 120–125 kV dan kuat arus 1000–1100 µA. Material uji ditempatkan pada ketinggian 60 cm dari detector untuk mendapatkan skala 1:1 terhadap benda uji sebenarnya. Pengamatan visual menunjukkan pembentukan beberapa spot yang mengindikasikan terjadinya oksidasi pada permukaan short pin PWR fuel dummy. Pengamatan terhadap citra radiografi yang dihasilkan dari pengujian radiografi sinar–X tidak menunjukkan adanya anomali dengan indikasi ­grey value pada arah aksial dan radial relatif homogen. Secara umum, berdasarkan hasil uji tak merusak, unjuk kerja short pin PWR fuel dummy relatif baik dengan tidak ditemukannya cacat yang signifikan. Sebagai konfirmasi terjadinya pembentukan oksida pada permukaan short pin PWR fuel dummy, perlu didukung oleh pengujian Eddy Current yang dilanjutkan dengan pengamatan mikrostruktur melalui pengujian metalografi.Kata kunci: Short pin, PWR, kelongsong, pasca iradiasi, uji tak merusak, radiografi sinar–X
FENOMENA KOROSI ZIRKALOY-2 DAN ZIRKALOY-4 DALAM MEDIA LARUTAN NaCl SECARA ELEKTROKIMIA Dian Anggraini; Maman Kartaman Ajiriyanto; Rosika Kriswarini; Yanlinastuti Yanlinastuti
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 21 No. 3 (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.2015.21.3.2465

Abstract

Zircaloy-2 and zircaloy-4 are used as cladding material in Light Water Reactor, (LWR), Boiling Water Reactor (BWR) and Pressurized Water Reactor (PWR). During its use in the spent fuel pool may interact between the cladding and seawater in case of abnormal condition. Chloride ion which contained in seawater has the potential for being corrosion in cladding material. The aim of this work was knowing zircaloy-2 and zircaloy-4 corrosion phenomena in NaCl medium by corrosion parameter determination with polarization resistance technique, tafel, and potentiodynamic. Samples are zircaloy-2 and zircaloy-4 pieces material with 1x1 cm dimension. The samples are mounting and soldered with copper wire, then the sample surface are polished by 1200 grade grinding paper. Corrosion test was done with corrosion cell that was completed by electrode standard (saturated calomel), electrode buffer (graphite) and work electrode (sample). Solvent medium was NaCl solution with concentration 3.5 %; 0.35 %; and 0.175 %. The result showed that ion Clˉ contained in NaCl which were concentration area from 0.175 % to 3.5 % did not affect corrosion mechanism. The corrosion type in potential range ± 250 mV to E­­corr was uniform corrosion in ZrO­2 oxide form. Zirkaloy-2 and zirkaloy-4 corrosion rate in 3.5 % NaCl concentration were obtained 6.39×10-3 and 7.40×10-3 mpy respectively. Corrosion phenomenon which was observed by potentiodynamic technique (± 1000 mV to Ecorr) showed that zirkaloy-2 and zirkaloy-4 underwent passivation and pitting corrosion. Pitting potential zirkaloy-2 and zirkaloy-4 were obtained -452.8 mV and -182.8 mV severally.
Co-Authors Dian Anggraini Refa Artika Rohmad Sigit Rosika Kriswarini Tri Yulianto Yanlinastuti Yanlinastuti