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Results 1-10 of 149 (Search time: 0.002 seconds).

1

Two-dimensional whole-core transport calculations of the OECD benchmark problem C5G7 MOX by the CRX code

Lee, GS; Cho, Nam-ZinresearcherPERGAMON-ELSEVIER SCIENCE LTDPROGRESS IN NUCLEAR ENERGY, v.45, no.2-4, pp.169 - 177, 2004

2

Barkhausen Noise in Ion Implanted Amorphous Ribbon

Song, H; Park, DG; Cho, Nam-ZinresearcherIEEE-INST ELECTRICAL ELECTRONICS ENGINEERS INCIEEE TRANSACTIONS ON MAGNETICS, v.46, no.2, pp.525 - 528, 2010-02

3

3-D Whole-Core Transport Calculations of the Extended OECD Benchmark Problem C5G7 MOX by the CRX Code

Lee, G.S.; Cho, Nam-ZinresearcherAmerican Nuclear SocietyTRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.89, no.0, pp.271 - 271, 2003

4

A spectral-galerkin coarse-mesh approach to solving the two-dimensional multigroup diffusion equations

Cheng, HW; Cho, Nam-ZinresearcherPERGAMON-ELSEVIER SCIENCE LTDANNALS OF NUCLEAR ENERGY, v.24, no.11, pp.883 - 900, 1997-07

5

Convergence analysis of the angular-dependent rebalance iteration method in X-Y geometry

Hong, S.G; Cho, Nam-ZinresearcherAmerican Nuclear SocietyTRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.80, pp.115 - 117, 1999-09

6

An analytic solution method for discrete ordinates transport equations in slab geometry with no spatial truncation error

Hong, S.G; Cho, Nam-ZinresearcherAmerican Nuclear SocietyTRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.81, pp.134 - 136, 1999

7

Adjoint and forward Monte Carlo coupled weight window generator for variance reduction

Ahn, J.G; Cho, Nam-ZinresearcherAmerican Nuclear SocietyTRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.82, pp.132 - 133, 2000-06

8

CRX: A code for rectangular and hexagonal lattices based on the method of characteristics

Hong, SG; Cho, Nam-ZinresearcherPERGAMON-ELSEVIER SCIENCE LTDANNALS OF NUCLEAR ENERGY, v.25, no.8, pp.547 - 565, 1998-05

9

Space-time reactor kinetics via monte carlo method

Cho, Nam-Zinresearcher; Yun, S.American Nuclear SocietyTRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.97, no.0, pp.494 - 497, 2007

10

Comparison of Monte Carlo simulation models for randomly distributed particle fuels in VHTR fuel elements

Yu, H.; Cho, Nam-ZinresearcherAmerican Nuclear SocietyTRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.95, no.0, pp.719 - 721, 2006

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