Results 1-10 of 11 (Search time: 0.006 seconds).
NO | Title, Author(s) (Publication Title, Volume Issue, Page, Issue Date) |
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An Improved Cost-Benefit Criterion Using Utility Theory Ra, KY; Chang, Soon-Heung, 1984 American Nuclear Society Annual Meeting, v.46, pp.523 - 525, American Nuclear Society, 1984-06 | |
Development of Finite Element Method of Body Fit Nodalization for Mixed Convection Analysis in Rod Bunbles Lee, GJ; Chang, Soon-Heung, The 3rd Internation Topical Meeting on Nuclear Reactor Plant Thermal Hydraulics and Operation, 1988 | |
Time Dependent Analysis of Quenching Phemonenon with the Nonuniformity of Water Penetration Pattern in Hot Debris Bed Lee, KW; Chang, Soon-Heung, The 2nd International Topical Meeting on Nucl. Power Plant Ther. Hydrau. and Operation, pp.26 - 33, 1986-04 | |
An Integral Approach to Evaluate Containment Heat Transfer Coefficients Choi, JH; Chang, Soon-Heung, 1984 American Nuclear Society Annual Meeting, pp.490 - 491, American Nuclear Society, 1984 | |
INTEGRATED APPROACH TO EVALUATE CONTAINMENT HEAT TRANSFER COEFFICIENTS. Chang, Soon-Heung; Choi, JH, 1984 American Nuclear Society Annual Meeting, v.46, pp.490 - 491, American Nuclear Society, 1984 | |
Fast Running System Code Development with Analytical Solution Technique and Marching Scheme Whang, DH; Lee, BH; Chang, Soon-Heung, '85 ANS National Heat Transfer Conference, pp.141 - 150, ANS, 1985-08 | |
결정론적 및 확률론적 안전분석을 위한 격납용기해석 Chang, Soon-Heung, 1983년 국내외 한국과학기술 학술회의 (원자력안전성 기술분과), pp.199 - 203, 1982 | |
The Two Step Characteristic Method to Reduce Numerical Diffusion Golay, MW; Chang, Soon-Heung, 1983 American Nuclear Society Mathematics and Computation Topical Meeting, American Nuclear Society, 1983 | |
Optimal Test Interval Modeling of Nuclear Safety System Using the Inherent Unavailability and Human Error Lee, JH; Yoon, WH; Hong, SY; Chang, Soon-Heung, The 3rd Internation Topical Meeting on Nuclear Power Plant Thermal Hydraulics and Operation, 1988 | |
A Numerical and Experimental Investigation of the Single-Phase Natural Circulation with Multiloop Baek, WP; Chang, Soon-Heung, International Nuclear Power Plant Thermal Hydraulics and Operations Topical Meeting, pp.1 - 10, 1984 |