| Neutronic analysis on molten salt reactor FUJI-12 using 235U as fissile material in LiF-BeF2-UF4 fuel AM Mabruri, RD Syarifah, IK Aji, RD Hanifah, A Arkundato, G Jatisukamto Eastern-European Journal of Enterprise Technologies 5 (2022), 6-12, 2022 | 7 | 2022 |
| Analisis Fraksi Volume Bahan Bakar Uranium Karbida Pada Reaktor Cepat Berpendingin Gas Menggunakan SRAC Code RD Syarifah, NN MH, Z Hanifah, I Karomah, AM Mabruri, A Arkundato Jurnal Jaring SainTek (JJST) 3 (1), 13-18, 2021 | 6 | 2021 |
| Analysis of core configuration for conceptual gas Cooled Fast Reactor (GFR) using OpenMC I Karomah, AM Mabruri, RD Syarifah, N Trianti Jurnal Teknologi Reaktor Nuklir Tri Dasa Mega 25 (2), 85-90, 2023 | 2 | 2023 |
| Validation of OpenMC Code Criticality Value Calculation for GFR Reactor with UN-PuN Fuel F Prasetya, AM Mabruri, I Karomah, RD Syarifah, IK Aji, N Trianti Journal of Physics: Conference Series 2734 (1), 012065, 2024 | 1 | 2024 |
| Analysis of variation minor actinide pin configurations Np-237, AM-241, and Cm-244 in UN-PuN fueled pressurized water reactor RD Syarifah, M Nasrullah, F Prasetya, AM Mabruri, A Arkundato, ... EUREKA: Physics and Engineering, 36-46, 2024 | 1 | 2024 |
| Comparative Analysis of Hexagonal and Square Fuel Pin Geometry Designs of GFR using Uranium Carbide Fuel MR Maulana, RD Syarifah, F Prasetya, AM Mabruri, A Arkundato, ... Journal of Energy, Material, and Instrumentation Technology 5 (3), 109-116, 2024 | | 2024 |
| Neutronic Analysis on Molten Salt Reactor (MSR) Using OpenMC Code With Variations of Geometry Core Fueled By LiF-BeF2-UF4 RD Syarifah, BA Putri, IK Aji El-Cezeri 11 (2), 152-159, 2024 | | 2024 |
| Validation of OpenMC Code for Low-cycle and Low-particle Simulations in the Neutronic Calculation AM Mabruri, RD Syarifah, IK Aji, A Arkundato, N Trianti Jurnal Ilmu Fisika 16 (2), 107-117, 2024 | | 2024 |
