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Results 1-10 of 18 (Search time: 0.004 seconds).

NO Title, Author(s) (Publication Title, Volume Issue, Page, Issue Date)
1
PRESSURE-DROP AND INTERFACE DRAG COEFFICIENT IN 2-PHASE FLOW OF SODIUM

No, Hee Cheonresearcher; KAZIMI, MS, NUCLEAR SCIENCE AND ENGINEERING, v.82, no.3, pp.235 - 242, 1982

2
Development of the LMFBR Accident Analysis Computer Code

No, Hee Cheonresearcher, NUCLEAR ENGINEERING AND TECHNOLOGY , v.16, no.2, pp.47 - 57, 1984-01

3
Study of the RETRAN Code for Upper Plenum Analysis in Small LOCA

No, Hee Cheonresearcher, NUCLEAR ENGINEERING AND TECHNOLOGY , v.16, no.3, pp.125 - 130, 1984-01

4
On the formulation of the virtual mass term in two fluid models

Kazimi, Mujid S.; No, Hee Cheonresearcher, NUCLEAR ENGINEERING AND DESIGN, v.95, pp.163 - 170, 1986-08

5
General Derivation of Two-Fluid Model

No, Hee Cheonresearcher, NUCLEAR ENGINEERING AND TECHNOLOGY , v.16, no.1, pp.1 - 10, 1984-03

6
ON SOOS EQUATIONS IN MULTIDOMAIN MULTIPHASE FLUID-MECHANICS

No, Hee Cheonresearcher, INTERNATIONAL JOURNAL OF MULTIPHASE FLOW, v.8, no.3, pp.297 - 299, 1982

7
AN IMPROVED NUMERICAL SCHEME WITH THE FULLY-IMPLICIT 2-FLUID MODEL FOR A FAST-RUNNING SYSTEM CODE

JEONG, JJ; No, Hee Cheonresearcher, NUCLEAR ENGINEERING AND DESIGN, v.104, no.2, pp.145 - 153, 1987-10

8
A NONEQUILIBRIUM 3-REGION MODEL FOR TRANSIENT ANALYSIS OF PRESSURIZED WATER-REACTOR PRESSURIZER

BAEK, SM; No, Hee Cheonresearcher; PARK, IY, NUCLEAR TECHNOLOGY, v.74, no.3, pp.260 - 266, 1986-09

9
Proposed Method to Predict Core Inventory History and Operator Time Margin during Small Break Accident

No, Hee Cheonresearcher, NUCLEAR ENGINEERING AND TECHNOLOGY , v.15, no.4, pp.219 - 228, 1983-01

10
3-DIMENSIONAL 2-FLUID CODE FOR U-TUBE STEAM-GENERATOR THERMAL DESIGN ANALYSIS

LEE, JY; No, Hee Cheonresearcher, NUCLEAR TECHNOLOGY, v.75, no.2, pp.205 - 214, 1986-11

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