| Passive cooling system in a nuclear spent fuel pool using a vertical straight wickless-heat pipe MH Kusuma, N Putra, AR Antariksawan, RA Koestoer, S Widodo, ... International Journal of Thermal Sciences 126, 162-171, 2018 | 66 | 2018 |
| Fuzzy probability based event tree analysis for calculating core damage frequency in nuclear power plant probabilistic safety assessment JH Purba, DTS Tjahyani, S Widodo, AS Ekariansyah Progress in Nuclear Energy 125, 103376, 2020 | 31 | 2020 |
| α-Cut method based importance measure for criticality analysis in fuzzy probability–Based fault tree analysis JH Purba, DTS Tjahyani, S Widodo, H Tjahjono Annals of Nuclear Energy 110, 234-243, 2017 | 28 | 2017 |
| Simulation of wickless-heat pipe as passive cooling system in nuclear spent fuel pool using RELAP5/MOD3. 2 MH Kusuma, NSD Putra, S Ismarwanti, S Widodo International Journal on Advanced Science, Engineering and Information …, 2017 | 23 | 2017 |
| Preliminary study on mass flow rate in passive cooling experimental simulation during transient using NC-queen apparatus M Juarsa, JH Purba, HM Kusuma, T Setiadipura, S Widodo Atom Indonesia 40 (3), 141-147, 2014 | 23 | 2014 |
| Simulation of Operational Conditions of FASSIP-02 Natural Circulation Cooling System Experimental Loop AR Antariksawan, S Widodo, M Juarsa, D Haryanto, MH Kusuma, N Putra Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear …, 2018 | 21 | 2018 |
| Numerical study on natural circulation characteristics in FASSIP-02 experimental facility using RELAP5 code AR Antariksawan, S Widodo, M Juarsa, D Haryanto, MH Kusuma, N Putra IOP Conference Series: Earth and Environmental Science 105 (1), 012090, 2018 | 18 | 2018 |
| Design of passive residual heat removal systems and application of two-phase thermosyphons: A review W Surip, N Putra, AR Antariksawan Progress in Nuclear Energy 154, 104473, 2022 | 13 | 2022 |
| Simulation of heat flux effect in straight heat pipe as passive residual heat removal system in light water reactor using RELAP5 Mod 3.2 MH Kusuma, N Putra, S Widodo, AR Antariksawan Applied Mechanics and Materials 819, 122-126, 2016 | 13 | 2016 |
| TRIGA 2000 Research Reactor Thermal-hydraulic Analysis Using RELAP/SCDAPSIM/MOD3. 4 AR Antariksawan, E Umar, S Widodo, M Juarsa, MH Kusuma International Journal of Technology 8 (4), 698-708, 2017 | 11 | 2017 |
| Analisis konveksi alam teras reaktor TRIGA berbahan bakar tipe pelat menggunakan COOLOD-N2 KA Sudjatmi, EP Hastuti, S Widodo, R Nazar Jurnal Teknologi Reaktor Nuklir TRI DASA MEGA 17 (2), 67-78, 2015 | 11 | 2015 |
| Analysis of natural convection in TRIGA reactor core plate types fueled using COOLOD-N2 KA Sudjatmi, N Reinaldy, PH Endiah, W Surip Jurnal Teknologi Reaktor Nuklir 17 (2), 67-78, 2015 | 11 | 2015 |
| Determining coolant flow rate distribution in the fuel-modified TRIGA plate reactor EP Hastuti, S Widodo, MD Isnaini, SG Rina, B Syaiful Journal of Physics: Conference Series 962 (1), 012045, 2018 | 9 | 2018 |
| A Backward method to estimate the Dai-ichi reactor core damage using radiation exposure in the environment PM Udiyani, S Kuntjoro, S Widodo Atom Indonesia 42 (2), 63-70, 2016 | 9 | 2016 |
| Performance analysis of AP1000 passive systems during Direct Vessel Injection (DVI) line break AS Ekariansyah, S Widodo Atom Indonesia 42 (2), 79-88, 2016 | 8 | 2016 |
| Analysis Of The Effect Of Elevation Difference Between Heater And Cooler Position In The Fassip-01 Test Loop Using Relap5 AS Ekariansyah, H Tjahjono, M Juarsa, S Widodo SIGMA EPSILON-Buletin Ilmiah Teknologi Keselamatan Reaktor Nuklir 19 (1), 2016 | 8 | 2016 |
| Penentuan koefisien dispersi atmosferik untuk analisis kecelakaan reaktor PWR di Indonesia PM Udiyani, S Widodo TRI DASA MEGA-JURNAL TEKNOLOGI REAKTOR NUKLIR 14 (2), 2012 | 8 | 2012 |
| Preliminary investigation of natural circulation stability in FASSIP-01 experimental facility using RELAP5 code AR Antariksawan, S Widodo, M Juarsa, G Giarno, MH Kusuma, N Putra AIP Conference Proceedings 2001 (1), 2018 | 7 | 2018 |
| The thermal-hydraulics analysis on radial and axial power fluctuation for AP1000 reactor MD Isnaini, S Widodo, M Subekti Jurnal Teknologi Reaktor Nuklir Tri Dasa Mega 17 (2), 79-86, 2015 | 7 | 2015 |
| Abnormal control rod withdrawal analysis for innovative research reactor using PARET-ANL codes EP Hastuti, S Tukiran, S Widodo, Sudarmono Kerntechnik 83 (2), 96-105, 2018 | 6 | 2018 |
