Experimental Investigation of Power Transient Critical Heat Flux for Downward Flow in Narrow Rectangular Channel Used in Research Reactor

von Kim, Hui Yung
Veröffentlicht in NURETH (18. : 2019 : Portland, Or.) 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019) ; Volume 6 of 9 (2020)

Special issue on the 7th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation, and Safety (NUTHOS-7) : [held on October 5 - 9, 2008 in Seoul, Korea]

Veröffentlicht 2009

Development of a Droplet Entrainment Correlation for a Vertical Upward Annular-Mist Flow (KAERI)

von Yoo, Jee Min
Veröffentlicht in NURETH (18. : 2019 : Portland, Or.) 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019) ; Volume 9 of 9 (2020)

Improvement of the Condensation Heat Transfer Model of the MELCOR Code Under the Thermal-Hydraulic Conditions of a PWR Containment

von Yoo, Jee Min
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 4 of 14 (2018)

Isŭnggwa chŏsŭngŭl sot'onghanŭn han'gŭl chemun

Veröffentlicht 2024