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pro vyhledávání: '"I. O. Dolinskii"'
Publikováno v:
Atomic Energy. 127:356-361
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 I
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9a1addc9a947883c84ba7f86ddaa197a
https://doi.org/10.1007/s10512-020-00636-0
https://doi.org/10.1007/s10512-020-00636-0
