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Showing results 1 to 8 of 8

1
Assessment of a DNB-type theoretical critical heat flux model for rod bundles with non-uniform axial power shapes

Han, KH; Hwang, DH; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.236, no.3, pp.223 - 231, 2006-02

2
Development of a thermal hydraulic analysis code for gas-cooled reactors with annular fuels

Han, KH; Seo, KW; Hwang, DH; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.236, no.2, pp.164 - 178, 2006-01

3
Development of a thermal-hydraulic analysis code for annular fuel assemblies

Han, KH; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.226, no.3, pp.267 - 275, 2003-12

4
Development of Heat Exchanger Thermal Performance Monitoring Program

Ha, AS; Heo, GY; Han, KH; Chang, Soon-Heung, 한국원자력학회 학술발표대회, 한국원자력학회, 2005-05

5
Development of Thermal-Hydraulic Analysis Code for Annular Fuel-Based Assemblies

Han, KH; Chang, Soon-Heung, The 3rd Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety, 2002

6
Thermal Hydraulic Analysis of Gas-Cooled Reactors with Annular Fuel Rods

Han, KH; Chang, Soon-Heung, 한국원자력학회 학술발표대회, 한국원자력학회, 2005-05

7
Thermal Hydraulic Analysis of Thorium Fuel Assemblies Loaded with Annular Seed Pins

Han, KH; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2002

8
Thermal Hydraulic Analysis of Thorium-based Annular Fuel Assemblies

Han, KH; Chang, Soon-Heung, The 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, 2003-10

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