Showing results 2621 to 2640 of 2827
Generation of Gamma-Ray Streaming Kernels Through Cylindrical Ducts Via Monte Carlo Method Kim, Dong Su; Cho, Nam Zin, NUCLEAR ENGINEERING AND TECHNOLOGY, v.25, no.1, pp.80 - 90, 1993-03 |
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 |
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 |
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 |
NEURAL NETWORK MODEL FOR ESTIMATING DEPARTURE FROM NUCLEATE BOILING PERFORMANCE OF A PRESSURIZED WATER-REACTOR CORE KIM, HK; LEE, SH; Chang, Soon-Heung, NUCLEAR TECHNOLOGY, v.101, no.2, pp.111 - 122, 1993-02 |
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 |
PRESSURIZED WATER-REACTOR CORE PARAMETER PREDICTION USING AN ARTIFICIAL NEURAL NETWORK KIM, HG; Chang, Soon-Heung; LEE, BH, NUCLEAR SCIENCE AND ENGINEERING, v.113, no.1, pp.70 - 76, 1993-01 |
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 |
차세대 원자로 설계를 위한 실증시험 노희천, NUCLEAR ENGINEERING AND TECHNOLOGY , v.25, no.2, pp.317 - 325, 1993-01 |
Interrelationship Between the Drift-flux Model and the Two-fluid Model No, Hee Cheon, NUCLEAR ENGINEERING AND TECHNOLOGY , v.25, no.2, pp.233 - 236, 1993-01 |
HIGH-SENSITIVITY READOUT OF 2D A-SI IMAGE SENSORS FUJIEDA, I; STREET, RA; WEISFIELD, RL; NELSON, S; NYLEN, P; PEREZMENDEZ, V; Cho, Gyuseong, JAPANESE JOURNAL OF APPLIED PHYSICS PART 1-REGULAR PAPERS SHORT NOTES REVIEW PAPERS, v.32, no.1A, pp.198 - 204, 1993-01 |
STRATEGY AND TOOL DEVELOPMENT FOR NUCLEAR-POWER-PLANT DESIGN SYNTHESIS WITH MEASUREMENT OF RELIABILITY AND SIMPLICITY MIN, BK; Chang, Soon-Heung, RELIABILITY ENGINEERING SYSTEM SAFETY, v.40, no.1, pp.69 - 76, 1993 |
A Stochastic Model for the Nuclide Migration in Geologic Media Using a Continuous Time Markov Process y.m. lee; c.h. kang; p.s. hahn; h.h. park; k.j. lee, NUCLEAR ENGINEERING AND TECHNOLOGY, v.25, no.1, pp.154 - 165, 1993 |
Formation and Transport of Radioactive Colloids in Porous Media jin yop chung; Lee, Kun Jai, WASTE MANAGEMENT, v.13, pp.599 - 611, 1993 |
A Nuclide Transport Model in the Fractured Rock Medium Using a Continuous Time Markov Process y.m. lee; c.h. kang; p.s. hahn; h.h. park; k.j. lee, NUCLEAR ENGINEERING AND TECHNOLOGY, v.25, no.4, pp.529 - 538, 1993 |
A Study on the Local Boiling of the Consolidated Spent Fuel Storage Pool chang ju lee; kun jai lee, NUCLEAR ENGINEERING AND TECHNOLOGY, v.25, no.1, pp.8 - 19, 1993 |
Characteristics of Boron Adsorption on Strong-Base Anion-Exchanging Resin jung won na; Lee, Kun Jai, ANNALS OF NUCLEAR ENERGY, v.20, no.7, pp.455 - 462, 1993 |
A Mass Conservative Numerical Solution of Vertical Water Flow and Mass Transport Equations in Unsaturated Porous Media seung cheol lim; Lee, Kun Jai, ANNALS OF NUCLEAR ENERGY, v.20, no.2, pp.91 - 99, 1993 |
A New Diffusion Nodal Method Based on Analytic Basic Function Expansion Noh J.M; Cho, Nam-Zin, TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.69, pp.462, 1993 |
PARALLEL SCHWARZ ALGORITHM WITH UNDER-RELAXED PSEUDO-BOUNDARY CONDITIONS IN DOMAIN DECOMPOSITION METHOD KIM, YH; Cho, Nam-Zin, INTERNATIONAL JOURNAL OF COMPUTER MATHEMATICS, v.48, no.3-4, pp.203 - 218, 1993 |
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