발행물
컨퍼런스
Korean Nuclear Society Spring Meeting, Jeju, Korea, May. 17-18, 2018.
2018
,
A Preliminary CHF Model Development and Data Comparison with Vertical Heaters under Pool Boiling Conditions
An Experimental Study on Flow Boiling Critical Heat Flux on Axisymmetric Sudden Expansion Channel
Critical heat flux enhancement of nuclear fuel cladding with a nano-porous oxide film by anodization
Effect of inclination angle and pressure for the CHF under the IVR-ERVC condition
Code Validation for the Behavior of Floating Absorber for Safety at Transient (FAST) under the Constant Density Condition