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Cited article:

Fuel performance code BERKUT-U to simulate the in-pile behavior of a single oxide or nitride fuel rod for fast reactors

A.V. Boldyrev, A.P. Dolgodvorov, I.O. Dolinskiy, V.D. Ozrin, P.V. Polovnikov, V.E. Shestak, V.I. Tarasov and A.V. Zadorozhnyi
Journal of Nuclear Materials 603 155417 (2025)
https://doi.org/10.1016/j.jnucmat.2024.155417