Zobrazeno 1 - 10
of 97
pro vyhledávání: '"Hyoung Kyu Cho"'
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 10, Pp 4307-4326 (2024)
This study investigates Equivalent Spherical Diameter (ESD) estimation at high inlet velocity pool scrubbing conditions using the Interfacial Area Transport Equation (IATE) diameter model including bubble-induced turbulence and interphase modeling. T
Externí odkaz:
https://doaj.org/article/cb11152ecb18484db9216bb4ef7aa9ad
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 8, Pp 3435-3449 (2024)
Considering that system analysis codes are used for the evaluation of the performance of Passive Safety Systems (PSSs), it is important to investigate the capability of the system analysis code to reliably predict the heat transfer and natural circul
Externí odkaz:
https://doaj.org/article/7fa2b32f71ca4f7a9aa24651c0f0b795
Moving reactor model for the MULTID components of the system thermal-hydraulic analysis code MARS-KS
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 11, Pp 4373-4391 (2022)
Marine reactor systems experience platform movement, and therefore, the system thermal-hydraulic analysis code needs to reflect the motion effect on the fluid to evaluate reactor safety. A moving reactor model for MARS-KS was developed to simulate th
Externí odkaz:
https://doaj.org/article/025a4d2f66a949c8b2a577c243a2626c
Publikováno v:
Frontiers in Energy Research, Vol 11 (2023)
Heat-pipe-cooled microreactors (HPRs) have advantages such as a compact design, easy transportation, and improved system reliability and stability. The core of an HPR consists of fuel rods and heat pipes in a monolith, which is a solid block structur
Externí odkaz:
https://doaj.org/article/3bf79495886b49cc959fca632b29e8f8
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 8, Pp 2488-2498 (2021)
The wall film-wise condensation plays an important role in the heat transfer processes of heat exchangers, refrigerators, and air conditioner. In the field of nuclear engineering, steam condensation is often utilized in safety systems to remove the c
Externí odkaz:
https://doaj.org/article/9cc73ece5445408f8db7c12b85829566
Autor:
Chi-Jin Choi, Hyoung Kyu Cho
Publikováno v:
Frontiers in Energy Research, Vol 10 (2022)
Advances in computational power have enabled the application of computational fluid dynamics (CFD) to nuclear reactor safety analyses, which require accurate predictability for two-phase flow in complex geometries. This study is aimed at validating C
Externí odkaz:
https://doaj.org/article/322a976195304ec8b29a286eab16da06
Publikováno v:
Nuclear Engineering and Technology, Vol 51, Iss 5, Pp 1231-1240 (2019)
Unlike land-based nuclear power plants, a marine or floating reactor is affected by external forces due to ocean conditions. These external forces can cause additional accelerations and affect each system and equipment of the marine reactor. Therefor
Externí odkaz:
https://doaj.org/article/da84277e48054677baf37c5e2b460fd6
Publikováno v:
Nuclear Engineering and Technology, Vol 50, Iss 1, Pp 54-67 (2018)
There have been recent efforts to establish methods for high-fidelity and multi-physics simulation with coupled thermal–hydraulic (T/H) and neutronics codes for the entire core of a light water reactor under accident conditions. Considering the com
Externí odkaz:
https://doaj.org/article/e76a04f1c1364452b9561b497c967d26
Publikováno v:
Nuclear Engineering and Technology, Vol 47, Iss 5, Pp 567-578 (2015)
In a nuclear reactor containment, wall condensation forms with noncondensable gases and their accumulation near the condensate film leads to a significant reduction in heat transfer. In the framework of nuclear reactor safety, the film condensation i
Externí odkaz:
https://doaj.org/article/490e934cdd6548688e4c81c4f13b34c3
Autor:
HAN YOUNG YOON, JAE RYONG LEE, HYUNGRAE KIM, IK KYU PARK, CHUL-HWA SONG, HYOUNG KYU CHO, JAE JUN JEONG
Publikováno v:
Nuclear Engineering and Technology, Vol 46, Iss 5, Pp 655-666 (2014)
The CUPID code has been developed at KAERI for a transient, three-dimensional analysis of a two-phase flow in light water nuclear reactor components. It can provide both a component-scale and a CFD-scale simulation by using a porous media or an open
Externí odkaz:
https://doaj.org/article/90093ba6486f432db91daa095937146f