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Prasetya, Fajri
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Analisis Perbandingan Desain Geometri Pin Bahan Bakar Heksagonal dan Persegi GFR Menggunakan Bahan Bakar Uranium Karbida Maulana, Muhammad Rizqi; Syarifah, Ratna Dewi; Prasetya, Fajri; Mabruri, Ahmad Muzaki; Arkundato, Artoto; Rohman, Lutfi
Journal of Energy, Material, and Instrumentation Technology Vol 5 No 3 (2024): Journal of Energy, Material, and Instrumentation Technology
Publisher : Departement of Physics, Faculty of Mathematics and Natural Sciences, University of Lampung

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.23960/jemit.v5i3.252

Abstract

Analisis Perbandingan Desain Geometri Pin Bahan Bakar Heksagonal dan Persegi GFR dengan Bahan Bakar Uranium Karbida telah dilakukan.Reaktor nuklir dari generasi I hingga IV mengalami perkembangan yang cukup signifikan. Salah satu reaktor generasi IV yang berpotensi dapat beroperasi di tahun 2030 adalah reaktor cepat jenis Gas-cooled Fast Reactor (GFR). Penelitian ini menggunakan reaktor GFR dengan bahan bakar uranium karbida (UC) dan daya input rendah sebesar 300MWth. Teras reaktor menggunakan desain geometri cylinder pancake dengan tinggi 100 cm dan diameter 240 cm. Penelitian ini bertujuan untuk membandingkan desain optimal variasi sel pin geometri heksagonal dan persegi untuk reaktor cepat tipe GFR. Penelitian dilakukan dengan menggunakan software SRAC 2006 dengan database JENDL 4.0. Tahapan yang dilakukan dalam penelitian ini adalah melakukan perhitungan konfigurasi inti homogen, perhitungan konfigurasi inti heterogen, kemudian melakukan variasi fraksi bahan bakar untuk menghasilkan data yang optimal pada variasi sel pin heksagonal dan sel pin persegi. Hasil menunjukkan bahwa desain optimal diperoleleh pada desain heterogen dengan persentase pengayaan uranium untuk F1, F2, dan F3 sebesar 11.5% - 12% - 12.5%. Desain optimal dengan persentase tersebut dicapai pada fraksi fuel 51% untuk geometri pin heksagonal dan 59% untuk geometri persegi.
The Effect of Adding Minor Actinide Fuel Rods on GFR Reactor in Radiopharmaceutical Waste Production Using OpenMC Program Syarifah, Ratna Dewi; Prasetya, Fajri; Mabruri, Ahmad Muzaki; Arkundato, Artoto; Trianti, Nuri
Science and Technology Indonesia Vol. 9 No. 4 (2024): October
Publisher : Research Center of Inorganic Materials and Coordination Complexes, FMIPA Universitas Sriwijaya

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.26554/sti.2024.9.4.857-865

Abstract

GFR is a generation IV reactor based on helium gas refrigeration capable of working at very high temperatures. The fast spectrum in this reactor makes it possible to use nitride-based fuel, namely Uranium Plutonium Nitride (UN-PuN). Adding minor actinide (MA) material to the primary fuel, UN-PuN can maximize reactor performance to near critical from the beginning to the end of burn-up. This study aims to analyze the effect of adding MA fuel rods to the heterogeneous core of 5 fuel variations (F1, F2, F3, F4, F5) on the probability of radiopharmaceutical waste production. The method in this research is to place MA fuel rods in this study using four designs based on the highest neutron flux value in one fuel assembly. The results of the neutron flux calculation show that the reactor’s active core’s central region (F1, F2, F3) needs to be added to MA fuel rods so that the resulting flux is more evenly distributed. The calculation of reactor criticality shows that Np fuel rod design 4 and Am fuel rod design 1 have the best keff value (keff ≈ 1) among other designs. The burn-up of MA fuel rods produces a minimal probability of producing Tc99m, Sr89, Y90, Rh105, Ag111, I231, and Sm15 radiopharmaceutical waste, even less than 1 kg.
Burn-up Analysis of TRIGA MARK II Research Reactor Fuel Elements Using OpenMC Program Prasetya, Fajri
Indonesian Journal of Physics Vol 35 No 2 (2024): Vol 35 No 2 2024
Publisher : Institut Teknologi Bandung

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.5614/itb.ijp.2024.35.2.2

Abstract

The TRIGA 2000 Bandung research reactor, a TRIGA MARK II type that has been operating critically since 1946, has experienced a significant decrease in criticality. This prompted researchers to implement a reshuffling scheme of 111 fuel elements to optimize burn-up throughout the reactor core area. Burn-up analysis of the TRIGA 2000 Bandung fuel elements has been carried out. This analysis aims to determine the burn-up capability and isotope production of each individual fuel element. The calculation uses the Monte Carlo-based OpenMC code that has gone through the verification and validation (V&V) stage based on the results of the MCNP simulation at 60% control rod withdrawal. Furthermore, the reactor power is varied by 100kW-500kW to see the reactor's ability to maintain criticality (k-eff) and obtain very small excess reactivity (ρ). The calculation of k-eff and ρ for 1 year (12 months) is applied in 2 ways, namely 5 hours per week and real-time. The results of real-time operations can optimize burn-up to near the critical point. The greater the power, the greater the number of neutrons for fission, thus accelerating the consumption of fissile material. The power of 200 kW was chosen for further analysis because at the end of the burn-up, the k-eff and ρ values ​​approached the critical point. The results of the percentage of U-235 and U-238 burn-up to be greater in the middle area of ​​the reactor core (ring B) and consistently decreased towards the edge of the reactor core (ring G). As a result, the mass production of Pu-239 was also very high in the ring B area. This also happened to toxic isotopes such as Sm-149, Xe-133, Xe-135 which tended to be high in that area. The high burn-up rate and isotope production became a reference for future research to apply the reshuffling concept to the TRIGA 2000 Bandung reactor core
Co-Authors Artoto Arkundato Lutfi Rohman Mabruri, Ahmad Muzaki Maulana, Muhammad Rizqi Syarifah, Ratna Dewi Trianti, Nuri