Researcher Page

사진

Cho, Nam-Zin (조남진) C-1950-2011

Department
Department of Nuclear and Quantum Engineering(원자력및양자공학과)
Co-author
Collaboration Network Collaboration Network
Website
http://nurapt.kaist.ac.krHomePage
Research Area

Keyword Cloud

Reload 더보기
1

Comparison of 1-D/1-D Fusion Method and 1-D/1-D Hybrid Method in Two-Dimensional Neutron Transport Problems: Convergence Analysis and Numerical Results

Yuk, Seungsu; Cho, Nam-ZinresearcherAMER NUCLEAR SOCNUCLEAR SCIENCE AND ENGINEERING, v.184, no.2, pp.151 - 167, 2016-10

2

Nuclear Reactor Transient Analysis by Continuous-Energy Monte Carlo Calculation Based on Predictor-Corrector Quasi-Static Method

Jo, Yugwon; Cho, Bumhee; Cho, Nam-ZinresearcherAMER NUCLEAR SOCNUCLEAR SCIENCE AND ENGINEERING, v.183, no.2, pp.229 - 246, 2016-06

3

Steady- and Transient-State Analyses of Fully Ceramic Microencapsulated Fuel with Randomly Dispersed Tristructural Isotropic Particles via Two-Temperature Homogenized Model-I: Theory and Method

Lee, Yoonhee; Cho, Bumhee; Cho, Nam-ZinresearcherKOREAN NUCLEAR SOCNUCLEAR ENGINEERING AND TECHNOLOGY, v.48, no.3, pp.650 - 659, 2016-06

4

Steady- and Transient-State Analyses of Fully Ceramic Microencapsulated Fuel with Randomly Dispersed Tristructural Isotropic Particles via Two-Temperature Homogenized Model-II: Applications by Coupling with COREDAX

Lee, Yoonhee; Cho, Bumhee; Cho, Nam-ZinresearcherKOREAN NUCLEAR SOCNUCLEAR ENGINEERING AND TECHNOLOGY, v.48, no.3, pp.660 - 672, 2016-06

5

Nonoverlapping local/global iterations with 2-D/1-D fusion transport kernel and p-CMFD wrapper for transient reactor analysis-II: Parallelization and Predictor-Corrector Quasi-Static method application

Cho, Bumhee; Cho, Nam ZinresearcherPERGAMON-ELSEVIER SCIENCE LTDANNALS OF NUCLEAR ENERGY, v.90, pp.284 - 302, 2016-04

6

Fission and Surface Source Iteration Method for Domain Decomposed Monte Carlo Whole-Core Calculation

Jo, Yugwon; Cho, Nam ZinresearcherAMER NUCLEAR SOCNUCLEAR SCIENCE AND ENGINEERING, v.182, no.2, pp.181 - 196, 2016-02

7

A Study of Neutronics Effects of the Spacer Grids in a Typical PWR via Monte Carlo Calculation

Tran, Xuan Bach; Cho, Nam ZinresearcherKOREAN NUCLEAR SOCNUCLEAR ENGINEERING AND TECHNOLOGY, v.48, no.1, pp.33 - 42, 2016-02

8

3D/2D rotational plane slicing method for 3D whole-core transport calculation

Yoo, Han Jong; Cho, Nam ZinresearcherPERGAMON-ELSEVIER SCIENCE LTDANNALS OF NUCLEAR ENERGY, v.87, pp.30 - 38, 2016-01

9

A nonoverlapping local/global iterative method with 2-D/1-D fusion transport kernel and p-CMFD wrapper for transient reactor analysis

Cho, Bumhee; Cho, Nam ZinresearcherPERGAMON-ELSEVIER SCIENCE LTDANNALS OF NUCLEAR ENERGY, v.85, pp.937 - 957, 2015-11

10

Few-group condensation via two-material coexisting ring model for fast reactor core analysis

Won, Jong Hyuck; Cho, Nam ZinresearcherPERGAMON-ELSEVIER SCIENCE LTDANNALS OF NUCLEAR ENERGY, v.83, pp.172 - 180, 2015-09

11

Whole-Core Transport Solutions with 2-D/1-D Fusion Kernel via p-CMFD Acceleration and p-CMFD Embedding of Nonoverlapping Local/Global Iterations

Yuk, Seungsu; Cho, Nam ZinresearcherAMER NUCLEAR SOCNUCLEAR SCIENCE AND ENGINEERING, v.181, no.1, pp.1 - 16, 2015-09

12

FEASIBILITY STUDY OF A DEDICATED NUCLEAR DESALINATION SYSTEM: LOW-PRESSURE INHERENT HEAT SINK NUCLEAR DESALINATION PLANT (LIND)

Kim, Ho Sik; No, Hee-Cheonresearcher; Jo, Yugwon; Wibisono, Andhika Feri; Park, Byung Ha; Choi, Jinyoung; Lee, Jeong-Ikresearcher; Jeong, Yong Hoonresearcher; Cho, Nam-ZinresearcherKOREAN NUCLEAR SOCNUCLEAR ENGINEERING AND TECHNOLOGY, v.47, no.3, pp.293 - 305, 2015-04

13

Steady- and transient-state analyses of fully ceramic microencapsulated fuel loaded reactor core via two-temperature homogenized thermal-conductivity model

Lee, Yoonhee; Cho, Nam-ZinresearcherPERGAMON-ELSEVIER SCIENCE LTDANNALS OF NUCLEAR ENERGY, v.76, pp.283 - 296, 2015-02

14

Whole-core transport solution via deterministic S-N transport/p-CMFD overlapping local/global calculation in hexagonal geometry problem

Yoo, Han Jong; Imron, Muhammad; Cho, Nam-ZinresearcherPERGAMON-ELSEVIER SCIENCE LTDANNALS OF NUCLEAR ENERGY, v.75, pp.468 - 475, 2015-01

15

Sodium-cooled fast reactor (SFR) fuel assembly design with graphite-moderating rods to reduce the sodium void reactivity coefficient

Won, Jong Hyuck; Cho, Nam Zinresearcher; Park, Hae Min; Jeong, Yong HoonresearcherELSEVIER SCIENCE SANUCLEAR ENGINEERING AND DESIGN, v.280, pp.223 - 232, 2014-12

16

Three-dimensional single-channel thermal analysis of fully ceramic microencapsulated fuel via two-temperature homogenized model

Lee, Yoonhee; Cho, Nam-ZinresearcherPERGAMON-ELSEVIER SCIENCE LTDANNALS OF NUCLEAR ENERGY, v.71, pp.254 - 271, 2014-09

17

Overlapping Local/Global Iteration Framework for Whole-Core Transport Solution

Cho, Nam-Zinresearcher; Yuk, Seungsu; Yoo, Han Jong; Yun, SunghwanAMER NUCLEAR SOCNUCLEAR SCIENCE AND ENGINEERING, v.175, no.3, pp.227 - 238, 2013-11

18

Efficient and accurate depletion calculations via two-block decomposition of nuclide concentration vector

Lee, Yoonhee; Cho, Nam-ZinresearcherPERGAMON-ELSEVIER SCIENCE LTDANNALS OF NUCLEAR ENERGY, v.53, pp.147 - 157, 2013-03

19

Comparison of stochastic models in Monte Carlo simulation of coated particle fuels

Yu, Hui; Cho, Nam-ZinresearcherQiangjiguang Yu LizishuQIANGJIGUANG YU LIZISHU/HIGH POWER LASER AND PARTICLE BEAMS, v.25, no.1, pp.143 - 146, 2013-01

20

A core design concept for multi-purpose research reactors

Seo, Chul-Gyo; Cho, Nam-ZinresearcherELSEVIER SCIENCE SANUCLEAR ENGINEERING AND DESIGN, v.252, pp.34 - 41, 2012-11

Load more items
Loading...

rss_1.0 rss_2.0 atom_1.0