Machine learning based system performance prediction model for reactor control Y Zeng, J Liu, K Sun, L Hu Annals of Nuclear Energy 113, 270-278, 2018 | 46 | 2018 |
Void reactivity decomposition for the Sodium-cooled Fast Reactor in equilibrium fuel cycle K Sun, J Krepel, K Mikityuk, S Pelloni, R Chawla Annals of Nuclear Energy 38 (7), 1645-1657, 2011 | 36 | 2011 |
Neutronic design features of a transportable fluoride-salt-cooled high-temperature reactor K Sun, LW Hu, C Forsberg Journal of Nuclear Engineering and Radiation Science 2 (3), 031003, 2016 | 27 | 2016 |
Fluoride-Salt-Cooled High-Temperature Test Reactor (FHTR): Goals, Options, Ownership, Requirements, Design, Licensing, and Support Facilities C Forsberg, LW Hu, J Richard, R Romatoski, B Forget, J Stempien, ... Massachusetts Institute of Technology, MIT-ANP-TR-154, 2014 | 27 | 2014 |
Thermal-hydraulic analyses of MIT reactor LEU transition cycles AJ Dave, K Sun, L Hu, SH Pham, EH Wilson, D Jaluvka Progress in Nuclear Energy 118, 103117, 2020 | 22 | 2020 |
Analysis of advanced sodium-cooled fast reactor core designs with improved safety characteristics K Sun EPFL, 2012 | 22 | 2012 |
Thermal-hydraulic analyses of transportable Fluoride salt–cooled high-temperature reactor with CFD modeling C Wang, K Sun, LW Hu, S Qiu, GH Su Nuclear Technology 196 (1), 34-52, 2016 | 21 | 2016 |
Tritium generation, release, and retention from in-core fluoride salt irradiations K Dolan, G Zheng, K Sun, D Carpenter, L Hu Progress in Nuclear Energy 131, 103576, 2021 | 18 | 2021 |
Neutronics modeling and analysis of the TMSR-SF1 fuel lattice and full core with explicit fuel particle distribution and random pebble loadings K Sun, J Wilson, S Hauptman, R Ji, AJ Dave, Y Zou, L Hu Progress in Nuclear Energy 109, 171-179, 2018 | 18 | 2018 |
Preliminary design and assessment of a heat pipe residual heat removal system for the reactor driven subcritical facility W Zhang, K Sun, C Wang, D Zhang, W Tian, S Qiu, GH Su Nuclear Engineering and Technology 53 (12), 3879-3891, 2021 | 13 | 2021 |
Numerical simulations of molten salt pebble-bed lattices AJ Dave, K Sun, L Hu Annals of Nuclear Energy 112, 400-410, 2018 | 13 | 2018 |
Transitional cores and fuel cycle analyses in support of MIT reactor low enriched uranium fuel conversion K Sun, AJ Dave, L Hu, EH Wilson, S Pham, D Jaluvka, T Heltemes Progress in Nuclear Energy 119, 103171, 2020 | 12 | 2020 |
Validation of a fuel management code MCODE-FM against fission product poisoning and flux wire measurements of the MIT reactor K Sun, M Ames, T Newton Jr, L Hu Progress in Nuclear Energy 75, 42-48, 2014 | 12 | 2014 |
Neutronics feasibility of an MIT Reactor–driven subcritical facility for the Fluoride‐salt–cooled High‐temperature Reactor K Sun, L Hu, C Forsberg International Journal of Energy Research 41 (14), 2248-2257, 2017 | 11 | 2017 |
Numerical assessment of packed-bed heat transfer correlations for molten salt AJ Dave, K Sun, L Hu Annals of Nuclear Energy 136, 107002, 2020 | 10 | 2020 |
A neutronics study for improving the safety and performance parameters of a 3600MWth Sodium-cooled Fast Reactor K Sun, J Krepel, K Mikityuk, R Chawla Annals of Nuclear Energy 53, 464-475, 2013 | 10 | 2013 |
ESFR core optimization and uncertainty studies A Rineiski, B Vezzoni, D Zhang, M Marchetti, F Gabrielli, W Maschek, ... IAEA FR13, 4-7, 2013 | 10 | 2013 |
Low enriched uranium (leu) conversion preliminary safety analysis report for the mit research reactor (mitr) K Sun, L Hu, EWA Bergeron, T Heltemes Technical report, Massachusetts Institute of Technology (MIT)., Cambridge …, 2017 | 9 | 2017 |
Uncertainty analysis of Transportable Fluoride-salt-cooled High-temperature Reactor (TFHR) using coupled DAKOTA with RELAP-3D method C Wang, K Sun, D Zhang, W Tian, S Qiu, GH Su Nuclear Engineering and Design 324, 269-279, 2017 | 8 | 2017 |
Thermal‐hydraulic design and analysis of a small modular molten salt reactor (MSR) with solid fuel C Wang, K Sun, D Zhang, W Tian, S Qiu, G Su International Journal of Energy Research 42 (3), 1098-1114, 2018 | 7 | 2018 |