5301 | 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 |
5302 | 결정론적 및 확률론적 안전분석을 위한 격납용기해석 Chang, Soon-Heung, 1983년 국내외 한국과학기술 학술회의 (원자력안전성 기술분과), pp.199 - 203, 1982 |
5303 | Studies of Water Packing Phenomenon in Safety Analysis Code No, Hee Cheon, Third Intl. Topical Meeting on Reactor Thermal Hydraulics, 1985 |
5304 | An Intellingent Controller of the Water Level of the PWR Steam Generator 노희천; 이재영, 한국원자력학회 추계발표회, 한국원자력학회, 1991 |
5305 | Interrelationship Between the Drift-Flax Model and the Two-Fluid Model 노희천, 한국원자력학회 추계발표회, 한국원자력학회, 1991 |
5306 | Thumal-Hydraulic Analysis of the Containment for Design of Passive Containment Cooling System 노희천; 박종하, 한국원자력학회 추계발표회, 한국원자력학회, 1991 |
5307 | Step-by-Step Integral Scaling Method No, Hee Cheon; Ishii, M, 한국원자력학회 춘계발표회, 한국원자력학회, 1991 |
5308 | Development of the Microcomputer-basect Adaptive Control System for Steam Generator Level Control 노희천; 배병환, 한국원자력학회 추계학술발표회, 한국원자력학회, 1985 |
5309 | Study of the RETRAN Code for Upper Plenum Analyis in Very Small LOCA 노희천, 국내외 한국과학기술자 종합학술대회, 1984 |
5310 | New Computational Method with a Fully-Implicit Scheme for a Real-Time Accident Simulator No, Hee Cheon; Jeong, Dong Wook, Third Intl. Topical Meeting on Reactor Thermal Hydraulics, 1985 |
5311 | Dynamic Modelling and Optimum Level Controller Design for Steam Generators in PWRs 노희천; 서규원, 한국원자력학회 추계학술발표회, 한국원자력학회, 1984 |
5312 | Direct Numerical Technique of Mathematical Programming for Optimal Control of Xenon Oscillation in Load Following Operation 노희천; 윤명현, 한국원자력학회 추계학술발표회, 한국원자력학회, 1984 |
5313 | Advanced Numerical Scheme for a Real Time Accident Simulator 노희천; 정동욱, 한국원자력학회 춘계학술발표회, 한국원자력학회, 1984 |
5314 | Development of a Two-Fluid, Three-Dimensional Sodium Boiling Code, THERMIT-6s for LMFBR Accident Analysis 노희천, 한국원자력학회 춘계학술발표회, 한국원자력학회, 1983 |
5315 | A Parametric Study of the High Pressure Melt Ejection from Two Different Scale Reactor Cavity Models 전문헌, Proc. of the 13th KAIF-JAIF Seminar on Nuclear Industry, pp.337 - 346, 1991 |
5316 | Analysis of Event Tree with Imprecise Inputs by Fuzzy Set Theory 전문헌, 한국원자력학회 '90 춘계학술발표회 논문집 (II), pp.783 - 794, 1990 |
5317 | A Parametric Study of Condensation-Induced Water Hammer in Nuclear Power Plants 전문헌, 한국원자력학회 '90 춘계학술발표회 논문집 (I), pp.463 - 477, 1990 |
5318 | A Correlation for Critical Pressure with Subcooled Upstream Conditions 전문헌, 한국원자력학회 '90 춘계학술발표회 논문집 (I), pp.357 - 370, 1990 |
5319 | Local Chemical and Thermal-Hydrai;oc Analysis of U-Tube Steam Generators No, Hee Cheon; Lee, Jae Young, Proc. of Third Intl. Topical Meeting on Nuclear Power Plant thermal-Hydraulics and Operation, 1988 |
5320 | Dynamic Scaling Method for Testing the performance of the Water Level Controller of Nuclear Steam Generators No, Hee Cheon; Lee, Jae Yong, Proc. of Third Intl. topical Meeting on Nuclear Power Plant Thermal-Hydraulics and Operations, 1988 |