NE-Journal Papers(저널논문)

Recent Items

Collection's Items (Sorted by Submit Date in Descending order): 2261 to 2280 of 2774

2261
Study on the Removal Efficiency of a TEDA Impregnated Charcoal Bed for Methyliodide under Dry Condition

장순흥; 조원진, NUCLEAR ENGINEERING AND TECHNOLOGY , v.16, no.2, pp.80 - 88, 1984

2262
급수관 파열사고 해석에 대한 운전변수와 모형변수의 불확실성 및 민감도 연구

이승혁; 김진수; 장순흥, NUCLEAR ENGINEERING AND TECHNOLOGY , v.19, no.1, pp.10 - 21, 1987-03

2263
Risk Model Development for PWR During Shutdown

Yoon, Won-Hyo; Chang, Soon Heung, NUCLEAR ENGINEERING AND TECHNOLOGY , v.21, no.1, pp.1 - 11, 1989-03

2264
A Determination of Bias between Calculational Methods for the Criticality Safety Analysis of Spent Fuel Storage Pool with Burnup Credit

이창건; 전병진; 노희천, NUCLEAR ENGINEERING AND TECHNOLOGY , v.18, no.1, pp.17 - 26, 1986-01

2265
DEVELOPMENT OF SOFTWARE FOR THE MICROSIMULATOR FOR THE KO-RI-NUCLEAR-POWER-PLANT UNIT-2

SEOK, H; No, Hee Cheon; CHO, SJ; PARK, SD; JUN, HY; LEE, YK, NUCLEAR TECHNOLOGY, v.106, no.3, pp.384 - 396, 1994-06

2266
A Stream Line Method to Remove Cross Numerical Diffusion and Its Application to The Solution of Navier - Stokes Equations

Chang, Soon Heung, NUCLEAR ENGINEERING AND TECHNOLOGY , v.16, no.1, pp.21 - 28, 1984

2267
Improvement of Pressurizer PROV System through Micro - Computer and PRA

이종호; 장순흥, NUCLEAR ENGINEERING AND TECHNOLOGY , v.17, no.4, pp.302 - 316, 1985

2268
General Derivation of Two-Fluid Model

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

2269
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

2270
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

2271
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

2272
Development of the LMFBR Accident Analysis Computer Code

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

2273
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

2274
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

2275
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

2276
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

2277
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

2278
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

2279
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

2280
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

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