Zobrazeno 1 - 10
of 243
pro vyhledávání: '"CONG Tenglong"'
Publikováno v:
Yuanzineng kexue jishu, Vol 56, Iss 11, Pp 2306-2317 (2022)
As the pressure and heat transfer boundaries between primary and secondary sides, the steam generator (SG) should be integrated during operation. However, SG suffers from the problems including vibration, wear, fatigue and corrosion, which will lead
Externí odkaz:
https://doaj.org/article/b92b5c3c62914870ad8269f678cab3f3
Publikováno v:
Yuanzineng kexue jishu, Vol 56, Iss 12, Pp 2725-2734 (2022)
LBE-cooled fast reactor (LBFR) has a promising application prospect in energy generation and transmutation of highlevel radioactive waste. Wirewrapped fuel rods are usually used in LBFR to reach high heat transfer efficiency and selfsupport.
Externí odkaz:
https://doaj.org/article/6fffc44bf5f64d78a3b0d5b687b2f6ec
Publikováno v:
He jishu, Vol 46, Iss 5, Pp 050605-050605 (2023)
BackgroundAs an innovative nuclear fuel assembly, the helical cruciform fuel (HCF) assembly has the characteristics of large specific heat transfer area, short heat conduction path, strong inter-channel mixing and free from the grid spacers. Compared
Externí odkaz:
https://doaj.org/article/fcef06818b9a440b8d42f9fc895a7820
Publikováno v:
He jishu, Vol 45, Iss 12, Pp 120605-120605 (2022)
BackgroundWhen steam generator tube rupture (SGTR) occurs in the lead-bismuth cooled fast reactor, high pressure water/steam flows into the primary side filled with high temperature liquid metal. According to the location and size of the rupture, the
Externí odkaz:
https://doaj.org/article/5bec42e1046a453c9fac51b7e1f36240
Publikováno v:
In Progress in Nuclear Energy January 2025 178
Publikováno v:
In Nuclear Materials and Energy December 2024 41
Publikováno v:
In Progress in Nuclear Energy December 2024 177
Publikováno v:
In Progress in Nuclear Energy December 2024 177
Publikováno v:
In Annals of Nuclear Energy November 2024 207
Publikováno v:
In Journal of Nuclear Materials November 2024 600