141 | THE MAXIMUM-ENTROPY METHOD FOR RECONSTRUCTION OF THE POINTWISE NEUTRON-FLUX DISTRIBUTION IN NODAL METHODS JUNG, WS; Cho, Nam-Zin, NUCLEAR SCIENCE AND ENGINEERING, v.108, no.4, pp.384 - 395, 1991-08 |
142 | RELIABILITY AND RISK ALLOCATION IN NUCLEAR-POWER-PLANTS - A DECISION-THEORETIC APPROACH PAPAZOGLOU, IA; Cho, Nam-Zin; BARI, RA, NUCLEAR TECHNOLOGY, v.74, no.3, pp.272 - 286, 1986-09 |
143 | 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-Zin, NUCLEAR ENGINEERING AND TECHNOLOGY, v.48, no.3, pp.650 - 659, 2016-06 |
144 | 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-Zin, NUCLEAR ENGINEERING AND TECHNOLOGY, v.48, no.3, pp.660 - 672, 2016-06 |
145 | 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-Zin, ANNALS OF NUCLEAR ENERGY, v.75, pp.468 - 475, 2015-01 |
146 | 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-Zin, NUCLEAR SCIENCE AND ENGINEERING, v.184, no.2, pp.151 - 167, 2016-10 |
147 | Nuclear Reactor Transient Analysis by Continuous-Energy Monte Carlo Calculation Based on Predictor-Corrector Quasi-Static Method Jo, Yugwon; Cho, Bumhee; Cho, Nam-Zin, NUCLEAR SCIENCE AND ENGINEERING, v.183, no.2, pp.229 - 246, 2016-06 |
148 | Steady- and transient-state analyses of fully ceramic microencapsulated fuel loaded reactor core via two-temperature homogenized thermal-conductivity model Lee, Yoonhee; Cho, Nam-Zin, ANNALS OF NUCLEAR ENERGY, v.76, pp.283 - 296, 2015-02 |