РАСЧЕТНЫЙ КОД БЕРКУТ

PUBLICATIONS

1. Veprev. D.P., et al. Development and validation of the BERKUT fuel rod module of the EUCLID/V1 integrated computer code // Annals of Nuclear Energy, 2018. – Vol. 113. – Pp. 237–245. https://www.sciencedirect.com/science/article/pii/S0306454917304280
2. Boldyrev A.V., et al. “BERKUT – Best Estimate Code for Modelling of Fast Reactor Fuel Rod Behaviour under Normal and Accidental Conditions” / International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17), (Proc. Int. Conf., Yekaterinburg, 2017), IAEA, Vienna (2018), Paper CN245-363. https://conferences.iaea.org/event/126/contributions/3517/
3. Boldyrev, A.V., et al. BERKUT code validation on post-reactor studies of irradiated BN-600 fuel rods with mixed uranium-plutonium nitride fuel // Atomic Energy, 2020. – Vol. 127. – Iss.6. – Pp. 356–361. https://www.researchgate.net/publication/340510547_Berkut_Code_Validation_on_Post-Reactor_Studies_of_Irradiated_Bn-600_Fuel_Rods_with_Mixed_Uranium-Plutonium_Nitride_Fuel
4. Boldyrev, A.V., et al., “Mechanistic fuel code BERKUT-U: self-consistent modeling of thermomechanical behavior of fuel elements and processes in the fuel of fast breeder reactors”/  International Conference on Fast Reactors and Related Fuel Cycles: Sustainable Clean Energy for the Future (FR22) (Proc. Int. Conf., Beijing, China, 2022), IAEA, Vienna (2022), Paper. https://conferences.iaea.org/event/218/contributions/18881/
5. M.S. Veshchunov, R. Dubourg, V.D. Ozrin, V.E. Shestak and V.I. Tarasov, Mechanistic modelling of urania fuel evolution and fission product migration during irradiation and heating // J. Nucl. Mater, 2007. – Vol. 362. – Pp. 327 335. https://www.sciencedirect.com/science/article/abs/pii/S0022311507001420