Visualization of Flow Inside Reactor Vessel Using 1/5-Down Scaled Model of Prototype Gen-1V Sodium Cooled Fast Reactor

von Kim, Woo Shik
Veröffentlicht in NURETH (18. : 2019 : Portland, Or.) 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019) ; Volume 5 of 9 (2020)

Design of the Downscaled Test Vessel for the Simulation of the Flow Distribution in An SFR Reactor

von Chang, Seok-Kyu
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 9 of 14 (2018)

A Study of Departure of Nucleate Boiling(DNB) Mechanisms on Forced Convective Channel Flow

von Kim, Seol Ha
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 11 of 14 (2018)

An Experimental Study on Measuring Volumetric Void Fraction Using Impedance Meter in 3x3 Rod Bundle Consisting of Metal Filter

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

An Experimental Study on Measuring Volumetric Void Fraction Using Impedance Meter in 3x3 Rod Bundle Consisting of Metal Filterconsisting of Metal Filter

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