NE-Journal Papers(저널논문)

Recent Items

Collection's Items (Sorted by Submit Date in Descending order): 2321 to 2340 of 2827

2321
General Derivation of Two-Fluid Model

No, Hee Cheon, NUCLEAR ENGINEERING AND TECHNOLOGY , v.16, no.1, pp.1 - 10, 1984-03

2322
A Procedure for Statistical Thermal Margin Analysis Using Response Surface Method and Monte Carlo Technique

김현군; 이영환; 김태운; 장순흥, NUCLEAR ENGINEERING AND TECHNOLOGY , v.18, no.1, pp.38 - 47, 1986

2323
Study of the RETRAN Code for Upper Plenum Analysis in Small LOCA

No, Hee Cheon, NUCLEAR ENGINEERING AND TECHNOLOGY , v.16, no.3, pp.125 - 130, 1984-01

2324
A Study on the Method of Combining Empirical Data and Deterministic Model for Fuel Failure Prediction

Cho, Byeong-Ho; Yoon, Young-Ku; Chang, Soon-Heung, NUCLEAR ENGINEERING AND TECHNOLOGY , v.19, no.4, pp.233 - 241, 1987-12

2325
Development of the LMFBR Accident Analysis Computer Code

No, Hee Cheon, NUCLEAR ENGINEERING AND TECHNOLOGY , v.16, no.2, pp.47 - 57, 1984-01

2326
A 9-Rule Fuzzy Logic Controller of the Nuclear Steam Generator

Lee, Jae-Young; No, Hee-Cheon, NUCLEAR ENGINEERING AND TECHNOLOGY , v.25, no.3, pp.371 - 380, 1993-01

2327
On the formulation of the virtual mass term in two fluid models

Kazimi, Mujid S.; No, Hee Cheon, NUCLEAR ENGINEERING AND DESIGN, v.95, pp.163 - 170, 1986-08

2328
A NEW APPROACH OF ANALYTIC BASIS FUNCTION EXPANSION TO NEUTRON DIFFUSION NODAL CALCULATION

NOH, JM; Cho, Nam-Zin, NUCLEAR SCIENCE AND ENGINEERING, v.116, no.3, pp.165 - 180, 1994-03

2329
Risk analysis of radioactive waste repository based on the time dependent hazard rate

Chang, Soon-Heung; Cho, WonJin, RADIOACTIVE WASTE MANAGEMENT AND THE NUCLEAR FUEL CYCLE, v.5, no.1, pp.63 - 80, 1984-06

2330
DEVELOPMENT STRATEGIES OF AN EXPERT SYSTEM FOR MULTIPLE ALARM PROCESSING AND DIAGNOSIS IN NUCLEAR-POWER-PLANTS

CHEON, SW; Chang, Soon-Heung; CHUNG, HY, IEEE TRANSACTIONS ON NUCLEAR SCIENCE, v.40, no.1, pp.21 - 30, 1993-02

2331
OPTIMAL FUEL LOADING PATTERN DESIGN USING AN ARTIFICIAL NEURAL-NETWORK AND A FUZZY RULE-BASED SYSTEM

KIM, HG; Chang, Soon-Heung; LEE, BH, NUCLEAR SCIENCE AND ENGINEERING, v.115, no.2, pp.152 - 163, 1993-10

2332
APPLICATION OF NEURAL NETWORKS TO MULTIPLE ALARM PROCESSING AND DIAGNOSIS IN NUCLEAR-POWER-PLANTS

CHEON, SW; Chang, Soon-Heung; CHUNG, HY; Bien, Zeung nam, IEEE TRANSACTIONS ON NUCLEAR SCIENCE, v.40, no.1, pp.11 - 20, 1993-02

2333
A PROBABILISTIC SAFETY CRITERION FOR CORE MELT FREQUENCY BASED ON THE DISTRIBUTION OF THE PUBLICS SAFETY GOALS

RA, KY; Lee, Byong-Whi; Chang, Soon-Heung, NUCLEAR TECHNOLOGY, v.101, no.2, pp.149 - 158, 1993-02

2334
SYSTEMATIC BAYES PRIOR-ASSIGNMENT BY COUPLING THE MINI-MAX ENTROPY AND MOMENT-MATCHING METHODS

YOON, WH; Chang, Soon-Heung, IEEE TRANSACTIONS ON RELIABILITY, v.43, no.2, pp.279 - 287, 1994-06

2335
DEVELOPMENT OF REAL-TIME CORE MONITORING-SYSTEM MODELS WITH ACCURACY-ENHANCED NEURAL NETWORKS

KOO, BH; KIM, HC; Chang, Soon-Heung, IEEE TRANSACTIONS ON NUCLEAR SCIENCE, v.40, no.5, pp.1347 - 1354, 1993-10

2336
A NEW CRITICAL HEAT-FLUX MODEL FOR LIQUID-METALS UNDER LOW HEAT-FLUX LOW-FLOW CONDITIONS

Chang, Soon-Heung; LEE, YB, NUCLEAR ENGINEERING AND DESIGN, v.148, no.2-3, pp.487 - 498, 1994-07

2337
PHYSICAL MODELING AND FINITE-ELEMENT METHOD FOR THE ANALYSIS OF LATERAL PHASE DISTRIBUTION PHENOMENA

LEE, GJ; Chang, Soon-Heung, INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, v.18, no.3, pp.333 - 342, 1991

2338
A STATISTICAL-MODEL FOR PREDICTION OF FUEL-ELEMENT FAILURE USING THE MARKOV PROCESS AND ENTROPY MINIMAX PRINCIPLES

CHOI, KY; Yoon, Young-Ku; Chang, Soon-Heung, NUCLEAR TECHNOLOGY, v.93, no.2, pp.195 - 205, 1991-02

2339
AN ALARM PROCESSING SYSTEM FOR A NUCLEAR-POWER-PLANT USING ARTIFICIAL-INTELLIGENCE TECHNIQUES

YANG, JO; Chang, Soon-Heung, NUCLEAR TECHNOLOGY, v.95, no.3, pp.266 - 271, 1991-09

2340
DEVELOPMENT OF A BUNDLE CORRECTION METHOD AND ITS APPLICATION TO PREDICTING CHF IN ROD BUNDLES

HWANG, DH; BAEK, WP; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.139, no.2, pp.205 - 220, 1993-02

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