Abstract
Abstract Neutronic and burnup assessment of a light water reactor (LWR)-based small modular reactor (SMR) core with transuranic fuel (TRU) was carried out and compared with UO2 fuel and mixed oxide fuel (MOX) for different core composition and configurations. Eight different cores were modeled by changing the fuel composition and loading pattern of four different fuel assemblies, namely, UO2, MOX, TRU, and annular UO2 fuel and simulated in open-source Monte Carlo code OpenMC. The radial neutron flux distribution and maximum to average flux ratio were studied. The lowest flux ratio was found in annular-2 models, whereas TRU models showed the highest value. The effect of enrichment, fuel burnup, moderator to fuel ratio, and soluble boron concentration on effective multiplication factor (keff) was investigated. Burnup analysis of fissionable materials and neutron poison was performed. Burnup-dependent fission rate of U-235, Pu-239, and Pu-241 was also studied. The composition of spent fuel at end of the cycle (EOC) was investigated and lower minor actinides (MAs) production was observed for TRU models. This analysis would help to determine the effectiveness and feasibility of these potential core configurations and to predict their neutronic behavior.
Sign-in/Register to access full text options 
Talk to us
Join us for a 30 min session where you can share your feedback and ask us any queries you have
Schedule a callMore From: Journal of Nuclear Engineering and Radiation Science
Disclaimer: All third-party content on this website/platform is and will remain the property of their respective owners and is provided on "as is" basis without any warranties, express or implied. Use of third-party content does not indicate any affiliation, sponsorship with or endorsement by them. Any references to third-party content is to identify the corresponding services and shall be considered fair use under The CopyrightLaw.
