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Cited article:

Evaluation of neutronic characteristics of composite uranium nitride (UN) and uranium carbide in uniform and seed-and-blanket fuel assembly configuration using OpenMC

Khurram Mehboob, Yahya A. Alzahrani, Majid Ali and Hannan Younis
Nuclear Engineering and Design 446 114602 (2026)
https://doi.org/10.1016/j.nucengdes.2025.114602

Padé Approximation for Solving Coupled Subgroup Neutron Transport Equations in Resonant Interference Media

Yongfa Zhang, Song Li, Lei Liu, Xinwen Zhao, Qi Cai and Qian Zhang
Mathematics 13 (18) 3003 (2025)
https://doi.org/10.3390/math13183003

Negative Weights and Weight Cancellation to Treat Anisotropic Scattering in Multigroup Monte Carlo Simulations

Parth Singh and Hunter Belanger
Nuclear Science and Engineering 1 (2025)
https://doi.org/10.1080/00295639.2025.2515347