Zobrazeno 1 - 10
of 35
pro vyhledávání: '"Sun Rock Choi"'
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 4, Pp 1125-1134 (2024)
This paper presents a validation study of the subchannel analysis code SLTHEN used for the core thermal-hydraulic design of the Prototype Gen-IV sodium-cooled fast reactor (PGSFR). To assess the performance of the ENERGY model of SLTHEN, four liquid
Externí odkaz:
https://doaj.org/article/5cc3ecf71c9148009f5d3e5f31dd9a86
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 10, Pp 3928-3942 (2022)
Thermal striping is a complex thermal–hydraulic phenomenon caused by fluid temperature fluctuations that can also cause high-cycle thermal fatigue to the structural wall of sodium-cooled fast reactors (SFRs). Numerical simulations using large-eddy
Externí odkaz:
https://doaj.org/article/58bfe7549c064f08830e0314f251e228
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 6, Pp 2262-2275 (2022)
The Korea Atomic Energy Research Institute (KAERI) studied the sodium-water reaction (SWR) minimized steam generator for the safety of the sodium-cooled fast reactor (SFR), and selected the copper bonded steam generator (CBSG) as the optimal concept.
Externí odkaz:
https://doaj.org/article/c8a038d7f41a4e089ed64ca86128327b
Publikováno v:
Nuclear Engineering and Technology, Vol 48, Iss 2, Pp 376-385 (2016)
A hexagonally arrayed 37-pin wire-wrapped rod bundle has been chosen to provide the experimental data of the pressure loss and flow rate in subchannels for validating subchannel analysis codes for the sodium-cooled fast reactor core thermal/hydraulic
Externí odkaz:
https://doaj.org/article/72473978cf6a41639c161ba1734caeb7
Publikováno v:
Energies, Vol 14, Iss 18, p 5846 (2021)
The steam generator in a nuclear power plant is a type of heat exchanger in which heat transfer occurs from the hot fluid in multiple channels to the cold fluid. Therefore, a uniform flow over multiple channels is necessary to improve heat exchanger
Externí odkaz:
https://doaj.org/article/b55be5cad40e42bfa584491388dd8edf
Publikováno v:
Magnetohydrodynamics (0024-998X). Jan-Mar2020, Vol. 56 Issue 1, p15-26. 12p.
Publikováno v:
Journal of Mechanical Science and Technology. 35:3469-3474
In the steam generator of a sodium-cooled fast reactor, heat transfer occurs from the primary sodium flow side at high temperature to the secondary water flow side at low temperature. Preventing the interaction between sodium and water in the heat ex
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::cc2cb2a93e665343ce5325f269fda074
https://doi.org/10.1007/s12206-021-0719-5
https://doi.org/10.1007/s12206-021-0719-5
Publikováno v:
Energies
Volume 14
Issue 18
Energies, Vol 14, Iss 5846, p 5846 (2021)
Volume 14
Issue 18
Energies, Vol 14, Iss 5846, p 5846 (2021)
The steam generator in a nuclear power plant is a type of heat exchanger in which heat transfer occurs from the hot fluid in multiple channels to the cold fluid. Therefore, a uniform flow over multiple channels is necessary to improve heat exchanger
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::36a2bf25c0cabcfcb1794a708fb82dd9
Publikováno v:
Nuclear Engineering and Design. 339:126-136
A detailed analysis of neutronics, core thermal-hydraulics, and fuel performance has been developed to predict the thermo-mechanical failures of all the metallic fuel rods in a sodium-cooled fast reactor. The neutronics analysis provides a reload pat
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9476bfc5dabfa6a865eb7cbfd4700d4d
https://doi.org/10.1016/j.nucengdes.2018.09.006
https://doi.org/10.1016/j.nucengdes.2018.09.006
Autor:
Dong-Jin Euh, Sun Rock Choi, Seok-Kyu Chang, Won Sik Yang, Hae Seob Choi, Hyungmo Kim, Hyeong-Yeon Lee
Publikováno v:
Annals of Nuclear Energy. 166:108810
Flow mixing between adjacent subchannels within a wire-wrapped hexagonal fuel rod bundle affects radial heat transfer and determines the maximum cladding temperature, which is a key parameter to ensure the fuel safety margin in a sodium-cooled fast r
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a541d05f50af24beddc82e4eca319b53
https://doi.org/10.1016/j.anucene.2021.108810
https://doi.org/10.1016/j.anucene.2021.108810