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Showing results 1 to 11 of 11

1
A Study on the Optimal Fuel Loading Pattern Design in Pressurized Water Reactor Using the Artificial Neural Network and Fuzzy Rule Based System

Lee, BH; Kim, HG; Chang, Soon-Heung, The IAEA Tech. Committee Meeting on Progress in Devel. & Design Aspects of Water-Cooled Rea, 1994

2
Development of an Expert System for Malfuction Diagnosis of Primary System in Nuclear Power Plant

Chung, HY; Park, IS; Hur, SK; Cheon, SW; Kim, HG; Chang, Soon-Heung, The 3rd Symposium on Expert Systems Application to Power Systems, pp.539 - 547, 1991-04

3
Development of an On-Line Expert System for Integrated Alarm Processing in Nuclear Power Plants

Kim, HG; Choi, SS; Chang, Soon-Heung, '94 ANS Winter Meeting, pp.121 - 123, 1994

4
Development of OASYS Using Rule- and Fuzzy-Based Expert System for Nuclear Power Plants

Kang, KS; Choi, SS; Kim, HG; Chang, Soon-Heung, '94 ANS Winter Meeting, pp.119 - 121, 1994

5
Development Strategies of an Intelligent Human-Machine Interface for Next Generation Nuclear Power Plants

Choi, SS; Park, JK; Hong, JH; Kim, HG; Chang, Soon-Heung, '96 NPIC & HMIT, 1996

6
Development Strategies on an Intelligent Software System for Total Operation and Maintenance of Nuclear Power Plants

Kim, HG; Choi, SS; Chang, Soon-Heung, The 7th International Conference on Human-Computer Interaction, 1997

7
Experimental Sutdy and Correlation Development of Critical Heat Flux Under Low Pressure and Low Flow condition

Kim, HC; Baek, WP; Kim, HG; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 1997

8
Intelligent Software System for the Advanced Control Room of a Nuclear Power Plant

Choi, SS; Park, JJ; Heo, GY; Kim, HG; Chang, Soon-Heung, 한국원자력학회 추계학술발표대회, pp.443 - 448, 한국원자력학회, 1997

9
KAIST Critical Heat Flux Correlation for Water Flow in Vertical Round Tubes

Baek, WP; Kim, HG; Chang, Soon-Heung, The 5th International Topical Meeting on Nuclear Thermal Hydraulics, Operations and Safety, 1997

10
Prediction of Nuclear Reactor Parameters Using Artificial Neural Network Models

Roh, MS; Cheon, SW; Kim, HG; Chang, Soon-Heung, The 2nd International Forum on the Expert Systems and Computer Simulation in Energy Eng., 1992-03

11
The Development Strategies on an Integrated Operator Decision Aid Support System in Nuclear Power Plants

Kang, KS; Jeong, HK; Yi, CU; Kim, HG; Chang, Soon-Heung, The IAEA Tech. Committee Meeting on Progress in Devel. & Design Aspects of Water-Cooled Reactor, pp.176 - 179, 1993

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