Ratiko Ratiko
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CRITICALITY SAFETY ANALYSIS OF THE DRY CASK DESIGN WITH AIR GAPS FOR RDNK SPENT PEBBLE FUELS STORAGECriticality Safety Analysis of the Dry Cask Design with Air Gaps for RDNK Spent Pebble Fuels Storage Pungky Ayu Artiani; Yuli Purwanto; Aisyah Aisyah; Ratiko Ratiko; Jaka Rachmadetin; Kuat Heriyanto
JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA Vol 23, No 3 (2021): October (2021)
Publisher : Pusat Teknologi Dan Keselamatan Reaktor Nuklir (PTKRN)

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/tdm.2021.23.3.6355

Abstract

Reaktor Daya Non-Komersial (RDNK) with a 10 MW thermal power has been proposed as one of the technology options for the first nuclear power plant program in Indonesia. The reactor is a High Temperature Gas-Cooled Reactor-type with spherical fuel elements called pebbles. To support this program, it is necessary to prepare dry cask to safely store the spent pebble fuels that will be generated by the RDNK. The dry cask design has been proposed based on the Castor THTR/AVR but modified with air gaps to facilitate decay heat removal. The objective of this study is to evaluate criticality safety through keff  value of the proposed dry cask design for the RDNK spent fuel. The keff  values were calculated using MCNP5 program for the dry cask with 25, 50, 75, and 100% of canister capacity. The values were calculated for dry casks with and without air gaps in normal, submerged, tumbled, and both tumbled and submerged conditions. The results of calculated keff  values for the dry cask with air gaps at 100% of canister capacity from the former to the latter conditions were 0.127, 0.539, 0.123, and 0.539, respectively. These keff values were smaller than the criticality threshold value of 0.95. Therefore, it can be concluded that the dry cask with air gaps design comply the criticality safety criteria in the aforementioned conditions.
Proses Oksidasi Biokimia untuk Pengolahan Limbah Simulasi Cair Organik Radioaktif Gunandjar Gunandjar; Zainus Salimin; Sugeng Purnomo; Ratiko Ratiko
Jurnal Forum Nuklir JFN Vol 4 No 1 Mei 2010
Publisher : BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (333.737 KB) | DOI: 10.17146/jfn.2010.4.1.220

Abstract

Kegiatan industri nuklir menimbulkan limbah cair organik seperti limbah detergen dari pencucian pakaian kerja, pelarut 30% TBP (tri-n-butyl phosphate) dalam kerosen dari pemurnian ataupun pengambilan uranium dari gagalan fabrikasi elemen bahan bakar, pelarut yang mengandung D2EHPA (di-2-ethyl hexyl phosphoric acid) dan TOPO (trioctyl phospine oxide) dalam kerosin dari pemurnian asam fosfat. Limbah tersebut bersifat bahan berbahaya dan beracun (B-3) serta radioaktif, oleh karena itu limbah tersebut harus diolah sehingga terjadi detoksifikasi B-3 dan dekontaminasi radionuklidanya. Telah dilakukan penelitian proses oksidasi biokimia pengolahan limbah simulasi cair organik radioaktif dari pencucian pakaian kerja menggunakan campuran bakteri mutan aerob bacillus sp, pseudomonas sp, arthrobacter sp, dan aeromonas sp. Limbah berkadar deterjen 1,496 g/L, aktivitas 10-1Ci/m3, dengan COD (Chemical Oxygen Demand) 128, BOD (Biological Oxygen Demand) 68 dan TSS (Total Suspended Solid) 1000 ppm, diolah dengan oksidasi biokimia dengan penambahan bakteri yang diberi nutrisi nitrogen dan fosfor, dan diaerasi. Hasilnya menunjukkan bahwa bakteri mampu menguraikan detergen menjadi karbon dioksida dan air sehingga memenuhi baku mutu air golongan B dengan kadar BOD dan COD berturut-turut berharga 6 dan 0 ppm, diperlukan waktu penguraian 106 jam untuk pemenuhan baku mutu tersebut. Semakin lama waktu proses memberikan kadar padatan total dalam lumpur semakin besar karena biomassa yang terbentuk dari massa koloni bakteri yang hidup dan mati semakin banyak.