| Comparative studies on plutonium and minor actinides utilization in small molten salt reactors with various powers and core sizes A Waris, IK Aji, S Pramuditya, S Permana, Z Su’ud Energy Procedia 71, 62-68, 2015 | 29 | 2015 |
| Thermal–hydraulic analysis of wire-wrapped SFR test subassemblies by subchannel analysis method S Pramuditya, M Takahashi Annals of Nuclear Energy 54, 109-119, 2013 | 27 | 2013 |
| Multi-criteria decision making for nuclear power plant selection using fuzzy AHP: Evidence from Indonesia AG Abdullah, MA Shafii, S Pramuditya, T Setiadipura, K Anzhar Energy and AI 14, 100263, 2023 | 18 | 2023 |
| Core design study for power uprating of integral primary system PWR S Pramuditya, M Takahashi Annals of Nuclear Energy 59, 16-24, 2013 | 17 | 2013 |
| Preliminary design study of small power 30-50 MWt experiment power reactor based on high temperature pebble bed gas cooled reactor technology D Irwanto, S Permana, A Pramutadi, S Pramuditya Journal of Physics: Conference Series 1127 (1), 012024, 2019 | 12 | 2019 |
| Evaluating the JEFF 3.1, ENDF/B-VII. 0, JENDL 3.3, and JENDL 4.0 nuclear data libraries for a small 100 MWe molten salt reactor with plutonium fuel C Wulandari, A Waris, S Permana, S Pramuditya Nuclear Science and Techniques 33 (12), 165, 2022 | 9 | 2022 |
| Plutonium and minor actinides utilization in FUJI-U1 molten salt reactor C Wulandari, A Waris, S Permana, S Pramuditya Journal of Physics: Conference Series 1204 (1), 012132, 2019 | 9 | 2019 |
| Moving Particle Semi-Implicit (MPS) utilization in analyzing the stratification behavior of immiscible liquid Y Yulianto, AN Hidayati, APA Mustari, M Ilham, S Pramuditya IOP Conference Series: Materials Science and Engineering 407 (1), 012189, 2018 | 8 | 2018 |
| Preliminary study of 20 MWth experiment power reactor based on pebble bed reactor D Irwanto, S Permana, S Pramuditya Journal of Physics: Conference Series 877 (1), 012058, 2017 | 7 | 2017 |
| Study on utilization of super grade plutonium in Molten Salt Reactor FUJI-U3 using CITATION code C Wulandari, A Waris, S Pramuditya, PAM Asril Journal of Physics: Conference Series 877 (1), 012021, 2017 | 7 | 2017 |
| Pengembangan kode komputer terintegrasi untuk studi desain awal pembangkit listrik tenaga nuklir jenis pwr S Pramuditya Institut Teknologi Bandung, 2007 | 7 | 2007 |
| Neutron flux distribution calculation for various spatial mesh of finite slab geometry using one-dimensional diffusion equation MA Shafii, WW Yunanda, D Fitriyani, S Pramuditya AIP Conference Proceedings 2180 (1), 2019 | 5 | 2019 |
| SUPEL scenario for PWR spent fuel direct recycling scheme A Waris, S Pramuditya, IK Aji, R Wirawan, N Nuha Applied Mechanics and Materials 575, 653-657, 2014 | 4 | 2014 |
| Effect of void-fraction on characteristics of several thorium fuel cycles in BWR A Waris, MA Shafii, S Pramuditya, R Kurniadi, Z Su’ud Energy conversion and management 63, 11-16, 2012 | 4 | 2012 |
| Neutronic Performances of 100 MWe MSR with Weapon Grade Plutonium Fuel C Wulandari, A Waris, S Permana, S Pramuditya Journal of Physics: Conference Series 1949 (1), 012019, 2021 | 3 | 2021 |
| Comparative Evaluation on Several Reactor Type of Actinide Closed-Cycle Schemes S Permana, A Pramutadi, S Pramuditya, D Irwanto Journal of Physics: Conference Series 1090 (1), 012011, 2018 | 3 | 2018 |
| Delayed neutrons effect on power reactor with variation of fluid fuel velocity at MSR Fuji-12 IK Aji, S Pramuditya, D Irwanto, A Waris Journal of Physics: Conference Series 799 (1), 012004, 2017 | 3 | 2017 |
| Computational fluid dynamics study on cross flow pressure drop for triangular array rod assemblies with wire S Pramuditya, M Takahashi, H Ninokata Annals of Nuclear Energy 87, 803-816, 2016 | 3 | 2016 |
| Preliminary study on LiF4-ThF4-PuF4 utilization as fuel salt of miniFUJI molten salt reactor A Waris, IK Aji, S Pramuditya, D Irwanto Journal of Physics: Conference Series 739 (1), 012004, 2016 | 2 | 2016 |
| Comparative studies on thorium fuel cycles of BWR with JENDL 3.2 and JEF 2.2 nuclear data libraries A Waris, S Pramuditya, YS Perkasa, I Arif International Journal of Nuclear Energy Science and Technology 2 8 (1), 1-11, 2014 | 2 | 2014 |
