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Keywords: OpenMC
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Journal Articles
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2023, 9(1): 011501.
Paper No: NERS-21-1139
Published Online: June 7, 2022
... and configurations. Eight different cores were modeled by changing the fuel composition and loading pattern of four different fuel assemblies, namely, UO 2 , MOX, TRU, and annular UO 2 fuel and simulated in open-source Monte Carlo code OpenMC. The radial neutron flux distribution and maximum to average flux ratio...