NE-Conference Papers(학술회의논문)

Recent Items

Collection's Items (Sorted by Submit Date in Descending order): 5201 to 5220 of 5619

5201
Decision Analysis for Nuclear Fuel Cycle Policy

이건재, 제 2 회 KAIF/KNS Joint Annual Conference, pp.28 - 30, 1987

5202
열교환기 튜브 조건이 비등 열전달에 미치는 영향에 대한 실험적 연구

전문헌, Proc. of the Korean Nuclear Society Autumn Meeting, Seoul, Korea, pp.257 - 264, 1994

5203
Assessment of Two Uncertainty Quantification Methods for Source Term Analysis

전문헌, Proc. of the Korean Nuclear Society Spring Meeting, Pohang, pp.497 - 502, 1994

5204
열교환기 튜브 구조가 열전달과 탱크 내부 온도에 미치는 영향에 대한 실험적 연구

전문헌, Proc. of the Korean Nuclear Society Spring Meeting, Pohang, pp.379 - 384, 1994

5205
Effects of Interfacial Shear Between the Gas and Turbulent Falling Liquid Film on Heat Transfer Coefficient

전문헌, Proc. of the Korean Nuclear Society Spring Meeting, Pohang, pp.317 - 323, 1994

5206
A Semi-Empirical Correlation for an Adiabatic Interfacial Friction Factor

전문헌, Proc. of Korean Nuclear Society Autumn Meeting, Seoul, Korea, pp.29 - 34, 1993

5207
An Experimental Study on the Flow Instabilities and Critical Heat Flux under Natural Circulation

Kim, YI; Chang, Soon-Heung, The 4th Internation Topical Meeting on Nuclear Thermal Hydraulics, Operations and Safety, 1994-04

5208
A Study on the Optimal Fuel Loading Pattern Design in Pressurized Water Reactor Using the Artificial Neural Network and Fuzzy Rule Based System

Lee, BH; Kim, HG; Chang, Soon-Heung, The IAEA Tech. Committee Meeting on Progress in Devel. & Design Aspects of Water-Cooled Rea, 1994

5209
Nonlinear Model-Based Robust Control of a Nuclear Reactor Using Adaptive PIF Gains and Variable Structure Controller

Park, M.G; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Autumn Meeting, pp.285 - 290, 1992-10

5210
Convergence Analysis of the Parallel Schwarz Algorithm with Under-Relaxation in Pseudo- Boundary Conditions

Kim, Y.H; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Autumn Meeting, Seoul, pp.223 - 228, 1992-10

5211
Generation of Gamma-Ray Streaming Kernels Through Cylindrical Ducts via Monte Carlo Method

Kim, D.S; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Meeting, pp.667 - 672, 1992-05

5212
An Expansion Method for Determining Asymptotic Stability Domains of Nonlinear Reactors

Yang, C.Y; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Meeting, pp.447 - 452, 1992-05

5213
Adomian Decomposition Method for the Reactor Point Kinetics

Cho, Y.C; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Meeting, pp.67 - 72, 1992-05

5214
Generation of Spatial Weighting Functions for Ex-Core Detectors by Adjoint Transport Calculation

Ahn, J.G; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Meeting, pp.15 - 20, 1992-05

5215
Development of Finite Element Method of Body Fit Nodalization for Mixed Convection Analysis in Rod Bunbles

Lee, GJ; Chang, Soon-Heung, The 3rd Internation Topical Meeting on Nuclear Reactor Plant Thermal Hydraulics and Operation, 1988

5216
Domain Decomposition Solution of the Neutron Diffusion Equation with an Iterative Parallel Algorithm on a Transputer Network

Kim, Y.H; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Autumn Annual Meeting, pp.125 - 130, 1991-10

5217
An Analytic Relations Method for the Calculation of Actinides Concentrations

Chang, D.I; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Annual Meeting, pp.499 - 504, 1991-05

5218
A Compute Code for Common-Cause Failure Analysis

Park, B.H; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Annual Meeting, pp.341 - 346, 1991-05

5219
Solution of Neutron Diffusion Equation on a Parallel Computer

Kim, Y.H; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Annual Meeting, pp.75 - 80, 1991-05

5220
Variance Reduction Techniques for Uncertainty Analysis of Fault Trees

Choi, J.S; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Annual Meeting, 1990-05

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