NE-Conference Papers(학술회의논문)

Recent Items

Collection's Items (Sorted by Submit Date in Descending order): 5221 to 5240 of 5619

5221
KIGEN - A Computer Code for Decay Heat Calculation by Analytic Relations

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

5222
An Observer-Theoretic Approach to Estimating Neutron Flux Distribution

Park, Y.H; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Annual Meeting, 1989-10

5223
An Improved Maximum Entropy Method for the Reconstruction Problem in Nodal Calculation

Jung, W.S; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Annual Meeting, 1989-10

5224
MARAS - A Computer Code for Semi-Markov Reliability Analysis of Alternating Systems

Lee, K.N; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Annual Meeting, 1989-05

5225
MARADD - A Computer Code for Semi-Markov Reliability Analysis of Test/Repair Policies for Standby Safety Systems

Jung, W.S; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Annual Meetign, 1989-05

5226
Maximum Entropy Method for the Reconstruction Problem in Nodal Calculation : Preliminary Results

Na, W.J; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Annual Meeting, 1989-05

5227
Optimal Control of Xenon Concentration via Observer Design

Woo, H.S; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Annual Meeting, 1989-05

5228
A Spectral Form Function Method for Reconstructing Pointwise Flux Distributions

Jeong, H.Y; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Annual Meeting, 1988-05

5229
SLIM/SVD - A Computer Code for Evaluation of System-Level Importance Measures in Probabilistic Safety Analysis of Nuclear Power Plants

Jung, W.S; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Annual Meeting, 1988-05

5230
On the Multiplicity of Power Distributions in a Nuclear Reactor under Reactivity Feedback Effects

Yang, C.Y; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Annual Meeting, 1987-10

5231
Determination of Intermediate-Level Performance Criteria for Improvement of Nuclear Power Plant Design and Operation

Jung, W.S; Cho, Nam-Zin, International Topical Meeting on Probabilistic Safety Assessment, pp.1366 - 1372, 1993-01

5232
Implementation of a Parallel Algorithm in 2-D Assembly Transport Calculation on a Transputer

Cho, Nam-Zin; Song, J.S, Proc. of the International Symposium on Numerical Transprot Theory, Moscow, Russia, pp.72 - 75, 1992-05

5233
A Lyapunov Function-Free Method for Stability Domains of Nonlinear Reactors

Yang, C.Y; Cho, Nam-Zin, Proc. of the 1992 Topical Meeting on Advances in Reactor Physics, v.2, pp.433 - 444, 1992-03

5234
Cell Homogenization Method for Strongly Heterogeneous Research Reactors

Lee, J.T; Lee, B.H; Cho, Nam-Zin; Oh, S.K, Proc. of the International Topical Meeting on Advanced in Math. Computation, and Reactor Physics, v.3, pp.1 - 12, 1991-04

5235
Reconstruction of Pointwise Neutron Flux Distribution via Minimum Cross-Entropy Principle

Jung, W.S; Cho, Nam-Zin, Proc. of the International Topical Meeting on Advances in Mathmatics, Computation, and Reactor Physi, pp.1 - 12, 1991-04

5236
A New Method for Reconstructing Pointwise Flux Distribution Based on Maximum Entropy Principle

Jung, W.S; Cho, Nam-Zin, Proc. of the International Conference on the Physics of Reactors:Operation, Design and Computation, v.2, pp.1 - 10, 1990-04

5237
Development of OASYS Using Rule- and Fuzzy-Based Expert System for Nuclear Power Plants

Kang, KS; Choi, SS; Kim, HG; Chang, Soon-Heung, '94 ANS Winter Meeting, pp.119 - 121, 1994

5238
Classification and Assessment of CHF Data in Round Tubes at Low Velocities

Chang, Soon-Heung, The IAEA Tech. Committee Meeting on Progress in Devel. & Design Aspects of Water-Cooled Reactor, pp.341 - 349, 1994

5239
A Mechanistic CHF Model for Liquid Metals Based on Flow Excursion Mechanism

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

5240
Characteristics of Radiocolloid

이건재, 한국원자력학회 학술발표회 ( 추계 ), pp.123 - 127, 1992

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