| A Conceptual Study of a Supercritical CO2-Cooled Micro Modular Reactor H Yu, D Hartanto, K Jangsik Energies 8 (12), 13938-13952, 2015 | 51 | 2015 |
| Comparison of different glass materials to protect the operators from gamma-rays in the PET using MCNP code M Zubair, E Ahmed, D Hartanto Radiation Physics and Chemistry 190, 109818, 2022 | 49 | 2022 |
| Kinetics parameters evaluation on the first core of the RSG GAS (MPR-30) using continuous energy Monte Carlo method PH Liem, T Surbakti, D Hartanto Progress in Nuclear Energy 109, 196-203, 2018 | 38 | 2018 |
| Alternative reflectors for a compact sodium-cooled breed-and-burn fast reactor D Hartanto, Y Kim Annals of Nuclear Energy 76, 113-124, 2015 | 32 | 2015 |
| Neutronics and transient analyses of a supercritical CO2-cooled micro modular reactor (MMR) H Yu, D Hartanto, BS Oh, JI Lee, Y Kim Energy Procedia 131, 21-28, 2017 | 28 | 2017 |
| Neutronics optimization and characterization of a long‐life SCO2‐cooled micro modular reactor Y Kim, D Hartanto, H Yu International Journal of Energy Research 41 (7), 976-984, 2017 | 26 | 2017 |
| Sensitivity and uncertainty analysis on the first core criticality of the RSG GAS multipurpose research reactor PH Liem, Zuhair, D Hartanto Progress in Nuclear Energy 114, 46-60, 2019 | 25 | 2019 |
| On the performance of nanofluids in APR 1400 PLUS7 assembly: Neutronics BA Khuwaileh, FI Al-Hamadi, D Hartanto, Z Said, M Ali Annals of Nuclear Energy 144, 107508, 2020 | 20 | 2020 |
| On the particle swarm optimization of cask shielding design for a prototype sodium-cooled fast reactor DW Lim, CW Lee, JY Lim, D Hartanto Nuclear Engineering and Technology 51 (1), 284-292, 2019 | 19 | 2019 |
| A compact breed and burn fast reactor using spent nuclear fuel blanket D Hartanto, Y Kim PHYSOR 2012, 2012 | 19 | 2012 |
| A comparative physics study for an innovative sodium‐cooled fast reactor (iSFR) D Hartanto, C Kim, Y Kim International Journal of Energy Research 42 (1), 151-162, 2018 | 18 | 2018 |
| Uranium enrichment reduction in the prototype gen-IV sodium-cooled fast reactor (PGSFR) with PBO reflector C Kim, D Hartanto, Y Kim Nuclear Engineering and Technology 48 (2), 351-359, 2016 | 17 | 2016 |
| A high-fidelity Monte Carlo evaluation of CANDU-6 safety parameters Y Kim, D Hartanto PHYSOR 2012, 2012 | 17 | 2012 |
| Estimation of public exposure during normal operation of unit-1 Barakah Nuclear Power Plant using GALE and HOTSPOT M Zubair, E Ahmed, D Hartanto South African Journal of Chemical Engineering 41, 235-243, 2022 | 16 | 2022 |
| Neutronics evaluation of a super-deep-burn with TRU fully ceramic microencapsulated (FCM) fuel in CANDU D Hartanto, Y Kim, F Venneri Progress in Nuclear Energy 83, 261-269, 2015 | 16 | 2015 |
| Development of a PARCS/Serpent model for neutronics analysis of the Dalat nuclear research reactor VP Tran, KC Nguyen, D Hartanto, HN Tran, VT Tran, VK Hoang, ... Nuclear Science and Technique 32, 15, 2021 | 14 | 2021 |
| Re-evaluation of the Fuel Temperature Coefficient of CANDU 6 YH Kim, D Hartanto Transactions of the Korean Nuclear Society Autumn Meeting 2011, 2011 | 14 | 2011 |
| Application of SCALE to Molten Salt Fueled Reactor Physics in Support of Severe Accident Analyses A Lo, FR Bostelmann, D Hartanto, BR Betzler, WA Wieselquist Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2022 | 13 | 2022 |
| Neutronics Assessment of Accident-Tolerant Fuel in Advanced Power Reactor 1400 (APR1400) D Hartanto, A Alshamsi, A Alsuwaidi, HA Hukal, M Zubair Atom Indonesia 46 (3), 177-186, 2020 | 13 | 2020 |
| Analysis of the first core of the Indonesian multipurpose research reactor RSG-GAS using the Serpent Monte Carlo code and the ENDF/B-VIII. 0 nuclear data library D Hartanto, PH Liem Nuclear Engineering and Technology 52 (12), 2725-2732, 2020 | 13 | 2020 |
