| Optimization study for thermal efficiency of supercritical water reactor nuclear power plant Y Su, KS Chaudri, W Tian, G Su, S Qiu Annals of Nuclear Energy 63, 541-547, 2014 | 47 | 2014 |
| Coupled analysis for new fuel design using UN and UC for SCWR KS Chaudri, W Tian, Y Su, H Zhao, D Zhu, G Su, S Qiu Progress in Nuclear Energy 63, 57-65, 2013 | 41 | 2013 |
| Development of sub-channel code SACoS and its application in coupled neutronics/thermal hydraulics system for SCWR KS Chaudri, Y Su, R Chen, W Tian, G Su, S Qiu Annals of Nuclear Energy 45, 37-45, 2012 | 41 | 2012 |
| Coupled neutronics/thermal-hydraulics for analysis of molten salt reactor Z Guo, J Zhou, D Zhang, KS Chaudri, W Tian, G Su, S Qiu Nuclear Engineering and Design 258, 144-156, 2013 | 38 | 2013 |
| Burnup dependent Monte Carlo neutron physics calculations of IAEA MTR benchmark KS Chaudri, MM Sikander Progress in Nuclear Energy 81 (c), 43–52, 2015 | 27 | 2015 |
| Preliminary transient thermal-hydraulic analysis for new coated UN and UC fuel options in SCWR H Zhao, D Zhu, KS Chaudri, S Qiu, W Tian, G Su Progress in Nuclear Energy 71, 152-159, 2014 | 26 | 2014 |
| Development and validation of a fast sub-channel code for LWR multi-physics analyses KS Chaudri, J Kim, Y Kim Nuclear Engineering and Technology 51 (5), 1218-1230, 2019 | 22 | 2019 |
| Development of TACOS code for loss of flow accident analysis of SCWR with mixed spectrum core D Zhu, H Zhao, W Tian, Y Su, K Saleem Chaudri, G Su, S Qiu Progress in nuclear energy 54 (1), 150-161, 2012 | 20 | 2012 |
| Coupled neutronics/thermal hydraulics evaluation for thorium based fuels in thermal spectrum SCWR KS Chaudri, W Tian, G Su, S Qiu Progress in Nuclear Energy 68, 55-64, 2013 | 15 | 2013 |
| Development and verification of LOOP: A Linkage of ORIGEN2. 2 and OpenMC A Gul, KS Chaudri, R Khan, M Azeem Annals of Nuclear Energy 99, 321-327, 2017 | 12 | 2017 |
| The effects of core zoning on optimization of design analysis of molten salt reactor Z Guo, C Wang, D Zhang, KS Chaudri, W Tian, G Su, S Qiu Nuclear Engineering and Design 265, 967-977, 2013 | 9 | 2013 |
| Beryllium as reflector of MNSR ST Muhammad, SI Ahmad, KS Chaudri, A Ahmad Annals of Nuclear Energy 35 (9), 1708-1712, 2008 | 9 | 2008 |
| Three-D core multiphysics for simulating passively autonomous power maneuvering in soluble-boron-free SMR with helical steam generator AAE Abdelhameed, KS Chaudri, Y Kim Nuclear Engineering and Technology 52 (12), 2699-2708, 2020 | 7 | 2020 |
| Comparative analyses of coated and composite UN fuel–Monte Carlo based full core LWR study H Ahmed, KS Chaudri, SM Mirza Progress in Nuclear Energy 93, 260-266, 2016 | 7 | 2016 |
| Development of coupled neutron physics/thermal hydraulics system using OpenMC and RELAP5 W Syed, KS Chaudri, M Sohail International Conference on Emerging Technologies (ICET) 2016, 2017 | 6 | 2017 |
| Monte Carlo modeling of the Pakistan Research Reactor-1 (PARR-1) MR Ali, R Khan, KS Chaudri, T Stummer Annals of Nuclear Energy 87, 584-590, 2016 | 6 | 2016 |
| Steady-state thermal hydraulic analysis of the equilibrium core of Pakistan research reactor-1 IH Bokhari, T Mahmood, KS Chaudri Annals of Nuclear Energy 34 (10), 836-838, 2007 | 6 | 2007 |
| Influence of evaluated data of fission product poisons on criticality A Ahmad, SI Ahmad, N Ahmad, KS Chaudri, TM Sahibzada, M Ahmad Progress in Nuclear Energy 51 (2), 334-338, 2009 | 4 | 2009 |
| What is the future for nuclear fission technology? A technical opinion from the Guest Editors of VSI NFT series and the Editor of the Journal Nuclear Engineering and Design F D’Auria, F Reventos, L Herranz, MS Perea, SC Alberola, J Freixa, ... Nuclear Engineering and Design 425, 113332, 2024 | 3 | 2024 |
| Review of Neutron Physics Analyses for Accident-Tolerant Fuel System KS Chaudri, M Alrwashdeh, HJ Ryu, SA Alameri Engineered Science 29, 1126, 2024 | 3 | 2024 |
Sikander Majid MirzaVerified email at pieas.edu.pk
