Results 1-10 of 18 (Search time: 0.008 seconds).
NO | Title, Author(s) (Publication Title, Volume Issue, Page, Issue Date) |
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PRESSURE-DROP AND INTERFACE DRAG COEFFICIENT IN 2-PHASE FLOW OF SODIUM No, Hee Cheon; KAZIMI, MS, NUCLEAR SCIENCE AND ENGINEERING, v.82, no.3, pp.235 - 242, 1982 | |
Development of the LMFBR Accident Analysis Computer Code No, Hee Cheon, NUCLEAR ENGINEERING AND TECHNOLOGY , v.16, no.2, pp.47 - 57, 1984-01 | |
Study of the RETRAN Code for Upper Plenum Analysis in Small LOCA No, Hee Cheon, NUCLEAR ENGINEERING AND TECHNOLOGY , v.16, no.3, pp.125 - 130, 1984-01 | |
On the formulation of the virtual mass term in two fluid models Kazimi, Mujid S.; No, Hee Cheon, NUCLEAR ENGINEERING AND DESIGN, v.95, pp.163 - 170, 1986-08 | |
General Derivation of Two-Fluid Model No, Hee Cheon, NUCLEAR ENGINEERING AND TECHNOLOGY , v.16, no.1, pp.1 - 10, 1984-03 | |
ON SOOS EQUATIONS IN MULTIDOMAIN MULTIPHASE FLUID-MECHANICS No, Hee Cheon, INTERNATIONAL JOURNAL OF MULTIPHASE FLOW, v.8, no.3, pp.297 - 299, 1982 | |
AN IMPROVED NUMERICAL SCHEME WITH THE FULLY-IMPLICIT 2-FLUID MODEL FOR A FAST-RUNNING SYSTEM CODE JEONG, JJ; No, Hee Cheon, NUCLEAR ENGINEERING AND DESIGN, v.104, no.2, pp.145 - 153, 1987-10 | |
A NONEQUILIBRIUM 3-REGION MODEL FOR TRANSIENT ANALYSIS OF PRESSURIZED WATER-REACTOR PRESSURIZER BAEK, SM; No, Hee Cheon; PARK, IY, NUCLEAR TECHNOLOGY, v.74, no.3, pp.260 - 266, 1986-09 | |
Proposed Method to Predict Core Inventory History and Operator Time Margin during Small Break Accident No, Hee Cheon, NUCLEAR ENGINEERING AND TECHNOLOGY , v.15, no.4, pp.219 - 228, 1983-01 | |
3-DIMENSIONAL 2-FLUID CODE FOR U-TUBE STEAM-GENERATOR THERMAL DESIGN ANALYSIS LEE, JY; No, Hee Cheon, NUCLEAR TECHNOLOGY, v.75, no.2, pp.205 - 214, 1986-11 |