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pro vyhledávání: '"Ye. T. Koyanbayev"'
Autor:
Ye. T. Koyanbayev, M. K. Skakov, E. G. Batyrbekov, I. I. Deryavko, Ye. Ye. Sapatayev, Ye. A. Kozhahmetov
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2019 (2019)
There are results of long-term thermal aging of samples of irradiated and nonirradiated FA jacket and nonirradiated fuel element cladding at a temperature range from 300 to 550°C in argon, to 600°C in air. Materials have been studied before and aft
Externí odkaz:
https://doaj.org/article/6616b808947e4408a25b8554b82d319c
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2019 (2019)
The analysis of the thermal condition of spent FA (fuel assembly) of BN-350 reactor in a six-place cask for dry storage is presented. Simulation of the thermal condition of the cask is conducted with finite elements method using ANSYS software. Calcu
Externí odkaz:
https://doaj.org/article/83757f4d7648486b80b4cabd665adbee
Publikováno v:
Materials Today: Proceedings. 25:17-23
The pulsed graphite reactor (IGR) is one of the oldest research reactors in the world. Since 1968, graphite with impregnated uranium with an enrichment of 90% in 235 uranium has been used as a fuel for the IGR reactor. Current conditions require the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::724ca451230570c6627b60ecb6033aea
https://doi.org/10.1016/j.matpr.2019.10.148
https://doi.org/10.1016/j.matpr.2019.10.148
Autor:
Erlan Batyrbekov, Ye. A. Kozhahmetov, M. K. Skakov, Ilya I. Deryavko, Ye. Ye. Sapatayev, Ye. T. Koyanbayev
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2019 (2019)
There are results of long-term thermal aging of samples of irradiated and nonirradiated FA jacket and nonirradiated fuel element cladding at a temperature range from 300 to 550°C in argon, to 600°C in air. Materials have been studied before and aft
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::dd59b3fd7997e103611b71386b716174
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2019 (2019)
The analysis of the thermal condition of spent FA (fuel assembly) of BN-350 reactor in a six-place cask for dry storage is presented. Simulation of the thermal condition of the cask is conducted with finite elements method using ANSYS software. Calcu
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::4715b00af5cd23f2b893c9972e356044