Results 1-10 of 219 (Search time: 0.009 seconds).
NO | Title, Author(s) (Publication Title, Volume Issue, Page, Issue Date) |
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Quantitative Evaluation of Reverse Dynamic Effects in steam Generators Using Spectrum Analysis No, Hee Cheon; Na, Man Gyun, 한국원자력학회 춘계발표회, pp.403 - 408, 한국원자력학회, 1993 | |
Hyperbolicity Breaking and The Effects of Entrance and Exit Geometry on Flooding No, Hee Cheon; Jeong, Ji Hwan; Lee, Jae Young, 1993 International Heat Transfer Conference, 1993 | |
Classification of Flooding Data According to the Type of Tube-End Geometries No, Hee Cheon; Jeong, Ji Hwan, 한국원자력학회 춘계발표회, pp.129 - 134, 한국원자력학회, 1993 | |
Scaling studies on spreading of molten corium in MARK-1 boiling water reactors No, Hee Cheon; Mamoru, Ishii, 27th National Heat Transfer Conference, v.87, no.283, pp.74 - 85, 1991-07-28 | |
Stepwise Integral Scaling Method for Severe Accident analysis and its Application to Corium Dispersion in Direct Containment Heating No, Hee Cheon; Ishii, M.; Zhang, G, Sixth International Topical Mtg on Nuclear Reactor Thermal Hydraulics, 1993 | |
Analytical and Experimental Studies of U-Tube Steam Generator in PWR in Natural Circulation, Pot-Boiling, and Tube-Uncovery Modes No, Hee Cheon; Sul, Y.S., International Conference on New Trends in Nuclear System Thermohydraulics, 1994 | |
Measurements of Void Fraction by an Improved Multi-Channel Conductance Void Meter No, Hee Cheon; Song, CH; Chung, MK, Proc. of the OECD/CSNI SPecialist Meeting on Advanced Instrumentation and Measurement Techniques, 1997 | |
Assessment and improvement of direct-contact condensation models with/without noncondensible gases in RELAP5/MOD3.2 No, Hee Cheon; Choi, KY; Bang, YS, 3rd ASME/JSME Joint Fluids Engineering Conference, 1999 | |
Validation Experiments and code development for passive safety systems of CP-1300 No, Hee Cheon, Proc. of the Int. Conf. on Future Nuclear Systems, GLOBAL '99, 1999 | |
Off-take Experiment at T-junction of Surge Line with Upward Branch in Horizontal Pipe No, Hee Cheon; Moon, YM, 2nd Japan-Korea Sym. on Nuclear Thermal Hydraulics and Safety, 2000 |
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