Zobrazeno 1 - 10
of 17
pro vyhledávání: '"Kyungdoo Kim"'
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 5, Pp 1890-1901 (2022)
We have assessed the applicability of the thermal-hydraulic system analysis code, SPACE, to a small modular reactor called SMART. For the assessment, the experimental data from a scale-down integral-test facility, SMART-ITL, were used. It was conform
Externí odkaz:
https://doaj.org/article/2f9f6a7b451a4db5bb1fec9c6c6344c2
Publikováno v:
Progress in Nuclear Energy. 109:45-52
Correlations for the droplet entrainment and deposition rates were developed to accurately predict its behavior in a horizontal annular flow. The Lopez de Bertodano et al. droplet entrainment rate correlation was evaluated and then modified based on
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1aa4516fa5fc5926872c2bfb600baa67
https://doi.org/10.1016/j.pnucene.2018.07.008
https://doi.org/10.1016/j.pnucene.2018.07.008
Publikováno v:
International Journal of Multiphase Flow. 97:197-205
Interfacial wave parameters, in this case the frequency, height, velocity, and slope, were investigated experimentally in a horizontal air-water stratified flow. Experiments were conducted with a parallel wire conductance sensor and PIV visualization
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::bdcecb8545d02d31301681b5cc84f8e9
https://doi.org/10.1016/j.ijmultiphaseflow.2017.08.009
https://doi.org/10.1016/j.ijmultiphaseflow.2017.08.009
Publikováno v:
AIChE Journal. 65
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::79820f4b68e042fbab0154d0964ba342
https://doi.org/10.1002/aic.16591
https://doi.org/10.1002/aic.16591
Publikováno v:
International Journal of Heat and Mass Transfer. 165:120726
Under the horizontal stratified flow condition, a droplet with a large interfacial area influences the mass, momentum, and heat transfer between the gas and liquid phases. In this study, we developed a force balance droplet entrainment rate model app
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d9534e4bbf71c7f7a42c70b44a417d8c
https://doi.org/10.1016/j.ijheatmasstransfer.2020.120726
https://doi.org/10.1016/j.ijheatmasstransfer.2020.120726
Publikováno v:
International Journal of Heat and Mass Transfer. 144:118613
An experimental study of the local droplet parameters for an atmospheric horizontal stratified wavy flow was conducted in a horizontal circular pipe with an inner diameter of 40 mm and a length of 5.5 m. The local distributions of the droplet fractio
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::31d8a6a35ae9a910cd801eaf62ed4560
https://doi.org/10.1016/j.ijheatmasstransfer.2019.118613
https://doi.org/10.1016/j.ijheatmasstransfer.2019.118613
Autor:
Kyoung-Ho Kang, Seok Cho, Kyungdoo Kim, Nam-Hyun Choi, Ki-Yong Choi, Yeon-Sik Kim, Hyun-Sik Park, Byong-Jo Yun, Won-Pil Baek, In-Cheol Chu
Publikováno v:
Nuclear Technology. 177:382-394
A postulated steam generator tube rupture (SGTR) event of the APR1400 (Advanced Power Reactor 1400 MWe) was experimentally investigated with the thermal-hydraulic integral effect test facility ATLA...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6d42832bf6281242a155ca0a4be0848e
https://doi.org/10.13182/nt12-a13482
https://doi.org/10.13182/nt12-a13482
Autor:
Se-Yun Kim, Tong-Soo Choi, Sang-Il Lee, Kyoung-Ho Kang, Yeon-Sik Kim, Joo-Sung Kim, Keo-hyoung Lee, Seok Cho, Suk Ku Sim, Ki-Yong Choi, Hyun-Sik Park, Won-Pil Baek, Eo-Hwak Lee, Cheol-Woo Kim, Sukho Lee, Kyungdoo Kim
Publikováno v:
Nuclear Engineering and Technology. 43:25-44
KAERI has been operating an integral effect test facility, ATLAS (Advanced Thermal-Hydraulic Test Loop for Accident Simulation), for accident simulations of advanced PWRs. Regarding integral effect tests, a database for major design basis accidents h
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::565915a5a76a2e93f2f32a4dd0a54ce2
https://doi.org/10.5516/net.2011.43.1.025
https://doi.org/10.5516/net.2011.43.1.025
Autor:
Jin-Hyuk Hong, Myeong-Soo Lee, Yong-Kwan Lee, Seung Wook Lee, Jae-Seung Suh, Kyungdoo Kim, Jae Jun Jeong
Publikováno v:
Nuclear Technology. 148:3-11
The Nuclear Steam Supply System (NSSS) thermal-hydraulic model adopted in the Korea Nuclear Plant Education Center (KNPEC)-2 simulator was provided in the early 1980s. The reference plant for KNPEC-2 is the Yong Gwang Nuclear Unit 1, which is a Westi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::45640cd99797752ee8ef928cd7931c35
https://doi.org/10.13182/nt04-a3543
https://doi.org/10.13182/nt04-a3543
Publikováno v:
International Journal of Multiphase Flow. 24:855-866
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f64976a4c297ab1de7206675a7dc989b
https://doi.org/10.1016/s0301-9322(97)00089-x
https://doi.org/10.1016/s0301-9322(97)00089-x