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Kaichao Sun
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Year
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
402018
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
352011
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
272014
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
262016
Analysis of advanced sodium-cooled fast reactor core designs with improved safety characteristics
K Sun
EPFL, 2012
232012
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
192020
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
172018
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
172016
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
142021
Numerical simulations of molten salt pebble-bed lattices
AJ Dave, K Sun, L Hu
Annals of Nuclear Energy 112, 400-410, 2018
122018
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
112021
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
112020
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
102017
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
102013
ESFR core optimization and uncertainty studies
A Rineiski, B Vezzoni, D Zhang, M Marchetti, F Gabrielli, W Maschek, ...
IAEA FR13, 4-7, 2013
102013
Numerical assessment of packed-bed heat transfer correlations for molten salt
AJ Dave, K Sun, L Hu
Annals of Nuclear Energy 136, 107002, 2020
92020
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
92017
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
92014
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
72018
Coupled 3D-neutronics/thermal-hydraulics analysis of an unprotected loss-of-flow accident for a 3600 MWth SFR core
K Sun, A Chenu, K Mikityuk, J Krepel, R Chawla
American Nuclear Society, Inc., 555 N. Kensington Avenue, La Grange Park …, 2012
72012
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