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Cited article:

Development and verification of transport and tally capabilities based on unstructured mesh in Reactor Monte Carlo code RMC

Jie Li, Pengfei Shen, Zhaoyuan Liu, Qing Li and Kan Wang
Nuclear Engineering and Technology 57 (6) 103404 (2025)
https://doi.org/10.1016/j.net.2024.103404