| Comparison of Monte Carlo calculation methods for effective delayed neutron fraction Y Nagaya, G Chiba, T Mori, D Irwanto, K Nakajima Annals of Nuclear Energy 37 (10), 1308-1315, 2010 | 41 | 2010 |
| Preliminary neutronic design of high burnup OTTO cycle pebble bed reactor T Setiadipura, D Irwanto, Z Zuhair Atom Indonesia 41 (1), 7-15, 2015 | 36 | 2015 |
| Burnup characteristics of a peu à peu fuel loading scheme in a 110MWt simplified pebble bed reactor D Irwanto, T Obara Journal of nuclear science and technology 48 (11), 1385-1395, 2011 | 21 | 2011 |
| Comparison of uranium plutonium nitride (U‐Pu‐N) and thorium nitride (Th‐N) fuel for 500 MWth gas‐cooled fast reactor (GFR) long life without refueling RD Syarifah, Z Su'ud, K Basar, D Irwanto, SC Pattipawaej, M Ilham International Journal of Energy Research 42 (1), 214-220, 2018 | 20 | 2018 |
| Design Study of 200MWth Gas Cooled Fast Reactor with Nitride (UN-PuN) Fuel Long Life without Refueling RD Syarifah, Y Yulianto, Z Su’ud, K Basar, D Irwanto MATEC Web of Conferences 82, 03008, 2016 | 20 | 2016 |
| The prospect of uranium nitride (UN-PuN) fuel for 25-100MWe gas cooled fast reactor long life without refuelling RD Syarifah, Z Su'Ud, K Basar, D Irwanto Journal of Physics: Conference Series 776 (1), 012103, 2016 | 17 | 2016 |
| Neutronic analysis of thorium nitride (Th, U233) N fuel for 500MWth gas cooled fast reactor (GFR) long life without refueling RD Syarifah, Y Yulianto, Z Su’ud, K Basar, D Irwanto Key Engineering Materials 733, 47-50, 2017 | 16 | 2017 |
| Reflector materials selection for core design of modular gas‐cooled fast reactor using OpenMC code H Raflis, I Muhammad, Z Su'ud, A Waris, D Irwanto International Journal of Energy Research 45 (8), 12071-12085, 2021 | 15 | 2021 |
| Fuel fraction analysis of 500 MWth gas cooled fast reactor with nitride (UN-PuN) fuel without refueling RD Syarifah, Z Su’ud, K Basar, D Irwanto Journal of Physics: Conference Series 799 (1), 012022, 2017 | 14 | 2017 |
| Burnup characteristics and fuel cycle economics of mixed uranium–thorium fuel in a simplified small pebble bed reactor D Irwanto, T Obara Journal of nuclear science and technology 49 (2), 222-229, 2012 | 14 | 2012 |
| Decay heat removal without forced cooling on a small simplified PBR with an accumulative fuel loading scheme D Irwanto, T Obara Annals of Nuclear Energy 60, 383-395, 2013 | 13 | 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 |
| Neutronic analysis of modular gas-cooled fast reactor for 5-25% of plutonium fuel using parallelization MCNP6 code H Raflis, M Ilham, Z Su’ud, A Waris, D Irwanto Journal of Physics: Conference Series 1493 (1), 012008, 2020 | 11 | 2020 |
| Enhancing the performance of a long-life modified CANDLE fast reactor by using an enriched 208Pb as coolant N Widiawati, Z Su’ud, D Irwanto, S Permana, N Takaki, H Sekimoto Nuclear Engineering and Technology 53 (2), 423-429, 2021 | 10 | 2021 |
| Study on calculation methods for the effective delayed neutron fraction D Irwanto, T Obara, G Chiba, Y Nagaya | 10 | 2011 |
| Study on fusion blanket with ceramic solid as tritium breeding material IR Maemunah, Z Su’ud, A Waris, D Irwanto Journal of Physics: Conference Series 2072 (1), 012004, 2021 | 9 | 2021 |
| Neutronic Comparison Study Between Pb (208)-Bi and Pb (208) as a Coolant In The Fast Reactor With Modified CANDLE Burn up Scheme. N Widiawati, Z Suud, D Irwanto, H Sekimoto Journal of Physics: Conference Series 1090 (1), 012071, 2018 | 9 | 2018 |
| Neutronic Analysis of UN-PuN Fuel use FI-ITB-CHI Code for 500MWth GFR Long Life Without Refueling RD Syarifah, Z Su’ud, K Basar, D Irwanto Journal of Physics: Conference Series 1090 (1), 012033, 2018 | 8 | 2018 |
| Comparative Study on Various Geometrical Core Design of 300 MWth Gas Cooled Fast Reactor with UN-PuN Fuel Longlife without Refuelling RD Syarifah, Z Su’ud, K Basar, D Irwanto Journal of Physics: Conference Series 877 (1), 012064, 2017 | 8 | 2017 |
| Initial core design analysis of lead (208)‐bismuth eutectic‐cooled reactor with radial fuel shuffling N Widiawati, Z Su'ud, D Irwanto, S Permana, N Takaki, H Sekimoto International Journal of Energy Research 45 (8), 12317-12324, 2021 | 7 | 2021 |
