20 results on '"Hong, Soon Joon"'
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2. Investigation of equivalent spherical bubble diameter at high inlet velocity pool scrubbing conditions
3. Implementation of chrome oxidation model into best-estimate system code for accident tolerant fuel
4. Effect of chromium coated zircaloy cladding of accident tolerant fuel on the best estimate LOCA methodology
5. Design of electric core simulator system (ECSS) for large-scale integral effect test facility
6. Prediction of nucleate boiling heat transfer on horizontal U-shaped heat exchanger submerged in a pool of water using MARS code
7. Development of CAP code for nuclear power plant containment: Lumped model
8. Scientific design of a large-scale sodium thermal–hydraulic test facility for KALIMER—Part I: Scientific facility design
9. Assessment of horizontal in-tube condensation models using MARS code. Part II: Annular flow condensation
10. Assessment of horizontal in-tube condensation models using MARS code. Part I: Stratified flow condensation
11. Condensation dynamics of submerged steam jet in subcooled water
12. Evaluation of recirculation sump performance for OPR1000 plant: Part I debris transport during the blow-down phase of LOCA
13. Efficacy and tolerability of a generic and a branded formulation of atorvastatin 20 mg/d in hypercholesterolemic Korean adults at high risk for cardiovascular disease: A multicenter, prospective, randomized, double-blind, double-dummy clinical trial
14. Acute and chronic effects of cigarette smoking on arterial stiffness
15. Development of Heat Transfer Model Package for Horizontal U-Shaped Heat Exchanger Submerged in Pool of Passive Safety System
16. Role of Deterministic Design Safety Criteria in Assuring Safety of Generation IV Reactors
17. Thermal-Hydraulic Analyses of Steam Generator Tube Rupture Accident for the Kori Nuclear Unit 1 Pressurized Thermal Shock Study
18. Study on post-blowdown of hot leg large break loss-of-coolant-accident in the view of mass and energy release analysis
19. Factors Affecting Coronary Flow Reserve: Measured by Transthoracic Doppler Echocardiography
20. Analysis of Main-Steam-Line-Break Accidents Using RETRAN-3D for Pressurized Thermal Shock Evaluation of the Kori Nuclear Unit-1 Power Plant
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