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| NO | Title, Author(s) (Publication Title, Volume Issue, Page, Issue Date) |
|---|---|
| Onset of Slugging Criterion Based on Characteristics and Stability Analyses of Transient One-Dimensional Two-Phase Flow Equations of Two-Fluid Model Chun, Moon Hyun, Proc. of the FIFTH International Topical Meeting on Nuclear Thermal Hydraulic, Operations, & Safety (NUTHOS-5)6, 1997 | |
| Heat Removal Capability of the Passive Residual Heat Removal System, Proc. of Passive Safety Features in Nuclear Installations Chun, Moon Hyun, Post-SMIRT 14 International Seminar 18, 1997 | |
| Critical Flow Rates of Subcooled Water Through Short Pipes with Small Diameters Chun, Moon Hyun, Proc. of the 8th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-8), pp.759 - 766, 1997 | |
| Flow Regime Characterization and Void Fraction Measurement by Capacitance Transducers Chun, Moon Hyun; Sung Chang-Kyung, Winter Annual Meeting of the American Society of Mechanical Engineers., 1984 | |
| Experimental investigation of flooding in air-water counter-current flow with a vertical adiabatic multi-rod bundle Chun, Moon Hyun; Chung Bub-Dong; Cha Jong-Hee, ASHE Winter Annual Meeting of the American Society of Mechanical Engineers, 1990, v.99, pp.237 - 242, 1990-11-25 | |
| A Critical Review of the Current PWR Containment Response Analysis Methodologies for Postulated Severe Accident Chun, Moon Hyun, Proc. of Third Int'l. Topical Meeting on Nuclear Power Plant thermal-Hydraulics and Operatins. (NUPTHO-3), 1988 | |
| Thermal Analysis of Wolsung Unit 1 (CANDU) Spent Fuel Dry Storage Canister Chun, Moon Hyun, 16th Biennial ANS Topical Meeting on Reactor Operations Experience, pp.98 - 104, 1993 | |
| Development of a Computer Code to Estimate the Fuel Rod Failure Using Primary Coolant Activities of Operating PWRs Chun, Moon Hyun, Proc. of the ASME 6th International Conference on Nuclear Engineering (ICONE-6), 1998 | |
| A Numerical Model for Analyses of Reflooding Phase of LOCA Chun, Moon Hyun, ASME Paper No.82-WA/HT-32, 1982 | |
| Analysis of Forced Convection Melting in a Vertical Channel for Applications to LMFBRs Post-Accident Fuel Relocation Chun, Moon Hyun, Proc. of the Third International Topical Meeting on Reactor Thermal Hydraulics Newport, Rhode Island, 1985 |
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