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All Journal Science and Technology Indonesia Jurnal Ilmu Fisika Journal of Energy, Material, and Instrumentation Technology
Mabruri, Ahmad Muzaki
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Astronomy Biochemistry, Genetics & Molecular Biology Chemical Engineering, Chemistry & Bioengineering Control & Systems Engineering Earth & Planetary Sciences Electrical & Electronics Engineering Energy Environmental Science Materials Science & Nanotechnology Physics

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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

Comparative Analysis of Hexagonal and Square GFR Fuel Pin Geometry Designs with Uranium Carbide Fuel has been carried out. Nuclear reactors from Generation I to IV have developed significantly, with Gas-cooled Fast Reactors (GFR) being a potential candidate for operation by 2030. This study focuses on a GFR reactor utilizing uranium carbide (UC) fuel with a low input power of 300 MWth. The reactor core adopts a cylindrical pancake geometry with 100 cm height and 240 cm diameter dimensions. The objective is to compare the optimal design between hexagonal and square pin cell geometries for GFR-type fast reactors. The study employs the SRAC 2006 software with the JENDL 4.0 database. The research involves homogenous core configuration calculations, heterogeneous core configuration calculations, and variations in fuel fraction to determine optimal data for hexagonal and square pin cell configurations. Results indicate that heterogeneous fuel configurations require fuel fractions of 51% for hexagonal pins and 59% for square pins, with comparable maximum power performance at End of Life (EOL) and Beginning of Life (BOL). It suggests that hexagonal pins are more efficient, requiring less fuel material to maintain reactor criticality over a 20-period burn-up.
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.
Validation of OpenMC Code for Low-cycle and Low-particle Simulations in the Neutronic Calculation Mabruri, Ahmad Muzaki; Syarifah, Ratna Dewi; Aji, Indarta Kuncoro; Arkundato, Artoto; Trianti, Nuri
Jurnal Ilmu Fisika Vol 16 No 2 (2024): September 2024
Publisher : Jurusan Fisika FMIPA Universitas Andalas

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.25077/jif.16.2.107-117.2024

Abstract

Validation of Low-Cycle and Low-Particle OpenMC Simulation Codes for Neutronics Calculations has been conducted. This study validates OpenMC, an evolving open-source neutron analysis code. Validation of Low-Cycle and Low-Particle Codes is crucial as it allows for effective calculations with minimal computational resources. Determining the convergence point of cycles and minimum particles in low-cycle and low-particle calculations enables maintaining calculation accuracy, thus providing sufficiently accurate results. This study demonstrates that a minimum of 15,000 particles, 100 cycles (30 inactive, 70 active), is required for low-cycle simulations. A comparison of k-eff calculation results with the SRAC code for MSR FUJI-12 at 7 burnup points (0-27 MWd/ton) yields a maximum error of 0.7%. These results validate the effectiveness of OpenMC in achieving accurate neutronic calculations with limited computational resources
Validation of OpenMC Code for Low-cycle and Low-particle Simulations in the Neutronic Calculation Mabruri, Ahmad Muzaki; Syarifah, Ratna Dewi; Aji, Indarta Kuncoro; Arkundato, Artoto; Trianti, Nuri
Jurnal Ilmu Fisika Vol 16 No 2 (2024): September 2024
Publisher : Jurusan Fisika FMIPA Universitas Andalas

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.25077/jif.16.2.107-117.2024

Abstract

Validation of Low-Cycle and Low-Particle OpenMC Simulation Codes for Neutronics Calculations has been conducted. This study validates OpenMC, an evolving open-source neutron analysis code. Validation of Low-Cycle and Low-Particle Codes is crucial as it allows for effective calculations with minimal computational resources. Determining the convergence point of cycles and minimum particles in low-cycle and low-particle calculations enables maintaining calculation accuracy, thus providing sufficiently accurate results. This study demonstrates that a minimum of 15,000 particles, 100 cycles (30 inactive, 70 active), is required for low-cycle simulations. A comparison of k-eff calculation results with the SRAC code for MSR FUJI-12 at 7 burnup points (0-27 MWd/ton) yields a maximum error of 0.7%. These results validate the effectiveness of OpenMC in achieving accurate neutronic calculations with limited computational resources
Co-Authors Artoto Arkundato Indarta Kuncoro Aji Lutfi Rohman Maulana, Muhammad Rizqi Prasetya, Fajri Syarifah, Ratna Dewi Trianti, Nuri