Zobrazeno 1 - 4
of 4
pro vyhledávání: '"Aleksey L. Izhutov"'
Autor:
Aleksandr V. Alekseev, Oleg I. Dreganov, Aleksey L. Izhutov, Irina V. Kiseleva, Vitaly N. Shulimov
Publikováno v:
Nuclear Energy and Technology, Vol 5, Iss 3, Pp 207-212 (2019)
To license nuclear fuel for nuclear power plants, data on the behavior of fuel elements (FE) under design-basis accidents are required. These data are obtained during tests of fuel assemblies (FA) and single fuel elements in research reactor channels
Externí odkaz:
https://doaj.org/article/3491ea6e612e48e49f45dc450caea866
Autor:
Vitaly N. Shulimov, Irina V. Kiseleva, Oleg Igorevich Dreganov, Aleksandr Veniaminovich Alekseev, Aleksey L. Izhutov
Publikováno v:
Nuclear Energy and Technology 5(3): 207-212
Nuclear Energy and Technology, Vol 5, Iss 3, Pp 207-212 (2019)
Nuclear Energy and Technology, Vol 5, Iss 3, Pp 207-212 (2019)
To license nuclear fuel for nuclear power plants, data on the behavior of fuel elements (FE) under design-basis accidents are required. These data are obtained during tests of fuel assemblies (FA) and single fuel elements in research reactor channels
Autor:
Irina. V. Dobrikova, Vladimir. A. Starkov, Aleksey. A. Sheldyakov, Gennadiy. V. Kulakov, Andrey. E. Novoselov, Valeriy. V. Iakovlev, Aleksey. L. Izhutov, Valeriy. Yu. Shishin, Vladimir. B. Suprun, Aleksandr. V. Vatulin, Vladimir. M. Kosenkov
Publikováno v:
Nuclear Engineering and Technology, Vol 45, Iss 7, Pp 859-870 (2013)
The paper summarizes the irradiation test and post-irradiation examination (PIE) data for the U-Mo low-enriched fuel that was irradiated in the MIR reactor under the RERTR Program. The PIE data were analyzed for both full-size fuel rods and mini-rods
Autor:
ALEKSEY. L. IZHUTOV, VALERIY. V. IAKOVLEV, ANDREY. E. NOVOSELOV, VLADIMIR. A. STARKOV, ALEKSEY. A. SHELDYAKOV, VALERIY. YU. SHISHIN, VLADIMIR. M. KOSENKOV, ALEKSANDR. V. VATULIN, IRINA. V. DOBRIKOVA, VLADIMIR. B. SUPRUN, GENNADIY. V. KULAKOV
Publikováno v:
Nuclear Engineering and Technology, Vol 45, Iss 7, Pp 859-870 (2013)
The paper summarizes the irradiation test and post-irradiation examination (PIE) data for the U-Mo low-enriched fuel that was irradiated in the MIR reactor under the RERTR Program. The PIE data were analyzed for both full-size fuel rods and mini-rods
Externí odkaz:
https://doaj.org/article/143849e5731f4b6b9c0242c5494a3303