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Results 21-30 of 52 (Search time: 0.006 seconds).

NO Title, Author(s) (Publication Title, Volume Issue, Page, Issue Date)
21
Analytic initialization of nonequilibrium iodine and xenon distributions for core transient simulation

Song, JS; Cho, Nam-Zin; Lee, BH; Zee, SQ, NUCLEAR TECHNOLOGY, v.116, no.2, pp.137 - 145, 1996-11

22
Extension of analytic function expansion nodal method to multigroup problems in hexagonal-z geometry

Cho, Nam-Zin; Kim, YH; Park, KW, NUCLEAR SCIENCE AND ENGINEERING, v.126, no.1, pp.35 - 47, 1997-05

23
Hybrid of AFEN and PEN methods for multigroup diffusion nodal calculation

Noh, Jae Man; Cho, Nam-Zin, TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.73, pp.438 - 440, 1995-12

24
Waveform Relaxation Method for Reactor Transient Analysis

Park, Keon-Woo; Cho, Nam-Zin, NUCLEAR ENGINEERING AND TECHNOLOGY, v.27, no.6, pp.845 - 852, 1995-12

25
The AFEN Method for Hexagonal Nodal Calculation and Reconstruction

Cho, Nam-Zin; Noh J.M, TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.71, pp.466, 1994

26
Domain Decomposition Parallel Solution of the Neutron Diffusion Equation

Kim, Y.H; Cho, Nam-Zin, TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.64, pp.311, 1991

27
Angle-Dependent Rebalance Factor Method for Nodal Transport Problems in X-Y Geometry

Hong, S.G; Cho, Nam-Zin, TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.79, pp.139, 1998

28
Wavelet Transform Decomposition and Denoising for Reactor Monitoring

Park, C.J; Cho, Nam-Zin, TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.76, pp.345 - 346, 1997

29
Determination of equivalent plutonium content in MOX fuel assemblies

Kim, Yong Bae; Cho, Nam-Zin, TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.74, pp.300 - 302, 1996-12

30
Graphite-Filled MOX Fuel Design for Fully Loaded PWR Cores

Jo, C.K; Cho, Nam-Zin; Kim, Y.H, TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.78, pp.227, 1998

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