Berkut Code Validation on Post-Reactor Studies of Irradiated Bn-600 Fuel Rods with Mixed Uranium-Plutonium Nitride Fuel

Autor:	V.I. Tarasov, V.D. Ozrin, A.V. Boldyrev, I. O. Dolinskii, S.Yu. Chernov, A. V. Zadorozhnyi
Rok vydání:	2020
Předmět:	Materials science 020209 energy Nuclear engineering chemistry.chemical_element 02 engineering and technology Uranium Nitride Rod Plutonium Coolant Nuclear Energy and Engineering chemistry 0202 electrical engineering electronic engineering information engineering Irradiation Code Validation
Zdroj:	Atomic Energy. 127:356-361
ISSN:	1573-8205 1063-4258
Popis:	An advanced version of the BERKUT-U/V2.1 code intended for modeling the behavior of fuel rods with oxide or nitride fuel in standard and emergency operating regimes of fast reactors with liquid-metal coolant is being developed at the Nuclear Safety Institute, Russian Academy of Sciences (IBRAE RAS), as part of the project Next-Generation Codes of Project Proryv (Breakthrough). The present work reports the results of the validation of an advanced version of the code based on post-reactor studies of BN-600 fuel rods (KETVS-1, -6) and BREST-OD-300 fuel rods (ETVS-5) with mixed uranium-plutonium nitride fuel, irradiated in the BN-600 reactor.
Databáze:	OpenAIRE
Externí odkaz:	https://explore.openaire.eu/search/publication?articleId=doi_________::9a1addc9a947883c84ba7f86ddaa197a https://doi.org/10.1007/s10512-020-00636-0 Zobrazit plný text záznamu Full text from SpringerLink