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

Li, Jie; Shen, Pengfei; Liu, Zhaoyuan; Li, Qing; Wang, Kan

doi:10.1016/j.net.2024.103404

Nuclear Engineering and Technology

2024

DOI: 10.1016/j.net.2024.103404

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

Jie Li,

Pengfei Shen,

Zhaoyuan Liu

et al.

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

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References 23 publications

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