Badan Tenaga Nuklir Nasional: Jurnal BATAN
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STERILISASI MIKROBA BUBUK TALC MENGGUNAKAN SINAR GAMMA (Co-60)
Full text linkKerusakan produk bedak talek umumnya disebabkan oleh pertumbuhan mikroba. Beberapa industri mengatasi masalah ini dengan menggunakan teknik pengawetan iradiasi sinar gamma (Cobalt-60). Penelitian ini mengidentifikasi jumlah mikroba yang tersisa dalam bedak talek dan struktur sel bakteri yang diiradiasi. Pada studi pendahuluan, proses iradiasi dilakukan dengan memberikan dosis iradiasi bedak talek yang terdiri dari 4 taraf yaitu 0kGy, 5kGy, 7kGy, dan 9kGy yang dilakukan di PT. Rel-ion Bekasi menggunakan sinar gamma irradiator (Co-60), dan dilanjutkan dengan uji mikrobiologi terhadap sisa mikroba dalam bedak talk yang diradiasi yang dilakukan di Laboratorium Biokimia Fakultas Sains Universitas Brawijaya. Pengujian terdiri dari penghitungan jumlah bakteri dengan metode plate count dan identifikasi struktur sel bakteri dominan menggunakan metode pewarnaan gram dan pengamatan mikroskopis. Hasil penelitian menunjukkan bahwa jumlah bakteri pada bedak talek menurun seiring dengan meningkatnya dosis iradiasi. Identifikasi struktur sel bakteri yang dominan pada bedak talk yang diiradiasi menunjukkan ciri-ciri bakteri Pseudomonas aeruginosa dengan koloni bulat, licin, putih, memberikan pigmen kehijauan pada medium, dan menunjukkan sel bakteri gram negatif, dengan struktur batang, kadang-kadang bergandengan dan bercabang tidak beraturan dan berwarna merah.Kerusakan produk bedak talek umumnya disebabkan oleh pertumbuhan mikroba. Beberapa industri mengatasi masalah ini dengan menggunakan teknik pengawetan iradiasi sinar gamma (Cobalt-60). Penelitian ini mengidentifikasi jumlah mikroba yang tersisa dalam bedak talek dan struktur sel bakteri yang diiradiasi. Pada studi pendahuluan, proses iradiasi dilakukan dengan memberikan dosis iradiasi bedak talek yang terdiri dari 4 taraf yaitu 0kGy, 5kGy, 7kGy, dan 9kGy yang dilakukan di PT. Rel-ion Bekasi menggunakan sinar gamma irradiator (Co-60), dan dilanjutkan dengan uji mikrobiologi terhadap sisa mikroba dalam bedak talk yang diradiasi yang dilakukan di Laboratorium Biokimia Fakultas Sains Universitas Brawijaya. Pengujian terdiri dari penghitungan jumlah bakteri dengan metode plate count dan identifikasi struktur sel bakteri dominan menggunakan metode pewarnaan gram dan pengamatan mikroskopis. Hasil penelitian menunjukkan bahwa jumlah bakteri pada bedak talek menurun seiring dengan meningkatnya dosis iradiasi. Identifikasi struktur sel bakteri yang dominan pada bedak talk yang diiradiasi menunjukkan ciri-ciri bakteri Pseudomonas aeruginosa dengan koloni bulat, licin, putih, memberikan pigmen kehijauan pada medium, dan menunjukkan sel bakteri gram negatif, dengan struktur batang, kadang-kadang bergandengan dan bercabang tidak beraturan dan berwarna merah
DETERMINING GAMMA SOURCE IN URANIUM MOLYBDENUM OF FUEL IN G.A SIWABESSY MULTI PURPOSE REACTOR
Full text link Nuclear fission reactions produce a lot of radionuclides that release energy, one of which is in the form of gamma radiation. Gamma radiation is produced by various types of radionuclides, and nuclear reactor fuel will produce different values of gamma intensity. Uranium Molybdenum (U7Mo-Al) is the type of nuclear fuel for future research reactors that possesses many advantages. For the application of molybdenum-based fuel, it is necessary to determine the resulting gamma radiation. The purpose is to determine the gamma radiation produced from molybdenum-based fuel with various densities. This study begins with the determination of the mass composition of the reactor component, calculations with ORIGEN2.1, and data output analysis. The U7Mo-Al density was varied, namely 2.96 gU/cm3, 3.85 gU/cm3, 4.44 gU/cm3, 5.43 gU/cm3, 6.91 gU/cm3, and 8.29 gU/cm3. The gamma radiation yield of U7Mo-Al is lower than that of uranium silicide (U3Si2) with the same density of 2.96 gU/cm3. The result will add to the justification for the superiority of U7Mo-Al compared to U3Si2/Al. For U7Mo-Al with densities of 3.85 gU/cm3, 4.44 gU/cm3, 5.43 gU/cm3, 6.91 gU/cm3, and 8.29 gU/cm3, the one that produced the lowest gamma radiation intensity is 3.85 gU/cm3 while the highest is 8.29 gU/cm3. This explains that the intensity of the gamma radiation produced is directly proportional to the fuel density. The low intensity of gamma radiation in molybdenum-based fuel can be used as a suggestion in shielding design to ensure the operational safety of reactors.
Study of Alternative Radiation Material Shielding for Gamma Radiation using Monte Carlo Simulation
No full textLead as the most commonly used material for radiation shielding but possessing toxic properties. This research aims to identify alternative, lead-free, and non-toxic materials for gamma radiation shielding through Monte Carlo simulations. Bismuth Oxide (Bi2O3), Barium Oxide (BaO), Tungsten Trioxide (WO3), Tungsten Dioxide (WO2), and Molybdenum Trioxide (MoO3) were selected as potential substitutes for lead. Pure lead (Pb) and Lead Oxide (PbO) were used for comparison. The simulation were performed using Particle Heavy Ion Tracking System (PHITS) software, with a gamma energy of 662 keV. The result of the simulation shows that the linear attenuation coefficient values for Pb and PbO were 0.902 mm-1 and 0.74 mm-1, respectively. Meanwhile, the simulation results of those simulated materials that are closest to Pb and PbO are Bi2O3 and WO2 with an attenuation coefficient of 0.71 mm-1. This simulation shows that for non-lead materials, BiO2 and WO2 have potential as alternative of non-lead radiation shielding
THE PRELIMINARY STUDY ON IMPLEMENTING A SIMPLIFIED SOURCE TERMS ESTIMATION PROGRAM FOR EARLY RADIOLOGICAL CONSEQUENCES ANALYSIS
No full textIndonesia possesses numerous potential sites for nuclear power plant development. A fast and comprehensive radiological consequences analysis is required to conduct a preliminary analysis of radionuclide release into the atmosphere, including source terms estimation. One simplified method for such estimation is the use of the Relative Volatility approach by Kess and Booth, published in IAEA TECDOC 1127. The objective of this study was to evaluate the use of a simple and comprehensive tool for estimating the source terms of planned nuclear power plants to facilitate the analysis of radiological consequences during site evaluation. Input parameters for the estimation include fuel burn-up, blow-down time, specific heat transfer of fuel to cladding, and coolant debit, using 100 MWe PWR as a case study. The results indicate a slight difference in the calculated release fraction compared to previous calculations, indicating a need to modify Keywords: Source terms, Relative volatility, Release fraction, PWR, SMAR
ANALYSIS OF CORE CONFIGURATION FOR CONCEPTUAL GAS COOLED FAST REACTOR (GFR) USING OPENMC
Full text linkThis study focused on a conceptual core configuration of Gas Cooled Fast Reactor (GFR), as part of a generation IV reactor. Uranium-plutonium carbide (UC-PuC) was used as reactor fuel and a Monte Carlo simulation method using OpenMC has been carried out. This study aims to find the composition of uranium-plutonium carbide fuel to use inside a fuel pin, making up a hexagonal prism fuel assembly arranged to form an entire core. A homogeneous and heterogeneous core configuration was considered in this study, while the plutonium percentage varied from 8%- 15%. For the homogenous core configuration, 10% was found as the optimum plutonium fraction with the value of %∆k/k =1, which was then used as a reference to make up a heterogeneous core configuration. A heterogeneous core with 3 radial fuel regions of F1 using 9% Pu fraction, F2 10%, and F3 11% showed the most stable result for 5-year burn-up with a %∆k/k of 0.7. The %∆k/k value was decreased by 0.3 due to the fission reaction that occurred more evenly in all 3 fuel regions of heterogeneous configuration, reducing the core power peaking factor. Keywords: Core configuration, GFR, OpenMC, Reactivity, Fission reactio
INVESTIGASI MODIFIKASI LUBANG PENGISIAN GAS HELIUM PADA DESAIN END PLUG BATANG UJI BAHAN BAKAR NUKLIR MENGGUNAKAN ANALISIS COMPUTATIONAL FLUID DYNAMICS
Full text linkTelah dilakukan investigasi terhadap desain modifikasi lubang pengisian gas helium pada end plug batang uji PRTF dengan metode simulasi CFD. Simulasi dilakukan untuk memprediksi apakah gas helium dapat mengalir dengan baik ke dalam kelongsong melalui desain modifikasi. Dari simulasi ini diharapkan dapat diperoleh data mengenai pengaruh perubahan bentuk dan dimensi dari lubang pengisian gas helium. Data tersebut selanjutnya akan digunakan sebagai panduan untuk menentukan desain modifikasi bisa berfungsi lebih baik sehingga dapat menggantikan desain original. Data masukan yang diperlukan untuk simulasi CFD adalah geometri dari model, jenis material yang digunakan, dan parameter kondisi tekanan dan waktu untuk persiapan proses pengelasan. Selanjutnya dilakukan proses simulasi CFD dengan mensimulasikan pengkondisian bahan sebelum proses las orbital TIG. Hasil simulasi menunjukkan bahwa desain modifikasi mampu mengalirkan gas helium ke dalam kelongsong dua kali lebih cepat dibanding dengan desain original. Selain itu hasil simulasi juga menunjukkan bahwa stabilitas desain modifikasi sama dengan desain original dalam mempertahankan tekanan gas helium pada tekanan 1,5 bar.Kata kunci: CFD, simulasi, PRTF, bahan bakar nuklir
ANALYSIS OF EYE LENS EFFECTIVE DOSE OF WORKERS DURING CARDIAC CATHERIZATION EXAMINATION IN A CATHLAB ROOM
Full text linkIn the current era, many radiological imaging technologies are used, one of which is the C-Arm equipment technology, which is capable of imaging three-dimensional patient objects in real time using fluoroscopy techniques. This study aims to obtain and evaluate the effective radiation dose received around the eye organs of radiation workers during cardiac catheterization. The main tool uses the C-Arm modality, and the TLD detector chip. The object of observation is the area around the eye organs of radiation workers consisting of one doctor and one nurse. Catheterization was carried out on 10 patients with different examination times. Research results: in the area around the eyes without protective glasses; the effective dose received by doctors' eyes ranges from 0.0011 to 0.0054 mSv, while for nurses it ranges from 0.0010 mSv to 0.0025 mSv. It was found that the effective dose received around the eye organs was lower than the dose value set by Perka Bapeten No. 8 of 2011 which is 20 mSv and ICRP 203 which is 500 mSv per year
RADIOLOGICAL HAZARDS ESTIMATION BY NATURAL RADIOACTIVITY IN WATER SAMPLES ALONG BATANG HARI RIVER, JAMBI
Full text linkIllegal mining activity is still operated along the watershed of Batang Hari, which could potentially be contaminated by natural radionuclides, which are Uranium-238 (238U), Thorium-232 (232Th), Radium-226 (226Ra), Polonium-210 (210Po), Kalium (40K), and Lead-210 (210Pb). This study aimed to measure activity concentrations of 238U, 232Th, and 40K in river water, groundwater, and drinking water samples along Batang Hari River, then calculate radiological hazard parameters in the sample. The sample collects from 3 different locations from 3 sample types Muaro Jambi District, Jambi City, District Batanghari, Tebo District, and Bungo District. The samples were measured using gamma spectrometry High Purity Germanium (HPGe) for 17 hours. The results showed that the average value of the radiology hazard parameters sample consists of Raeq 0,307653, AEDE that is 1,771 x10-6, and each external and internal hazard index are 0,00083 and 0,00155, respectively. The radiological hazard parameters in water samples along Batang Hari River, Jambi, are below the limit recommended that Raeq is 370 Bq.L-1, AEDE is 1 mSv.y-1, and hazard index Hex and Hin are 1. This study showed that the water is safe and fulfills the radiological aspect of water quality requirements