NE-Conference Papers(학술회의논문)

Recent Items

Collection's Items (Sorted by Submit Date in Descending order): 5301 to 5320 of 5619

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

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