Steady- and transient-state analyses of fully ceramic microencapsulated fuel loaded reactor core via two-temperature homogenized thermal-conductivity model von Lee, Yoonhee, Cho, Nam Zin

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Inline critical boron concentration search with p-CMFD feedback in whole-core continuous-energy Monte Carlo simulation von Jo, YuGwon, Cho, Nam Zin

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A Study of Neutronics Effects of the Spacer Grids in a Typical PWR via Monte Carlo Calculation von Tran, Xuan Bach, Cho, Nam Zin

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Steady- and Transient-State Analyses of Fully Ceramic Microencapsulated Fuel with Randomly Dispersed Tristructural Isotropic Particles via Two-Temperature Homogenized Model—I: Theo... von Lee, Yoonhee, Cho, Bumhee, Cho, Nam Zin

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Steady- and Transient-State Analyses of Fully Ceramic Microencapsulated Fuel with Randomly Dispersed Tristructural Isotropic Particles via Two-Temperature Homogenized Model—II: App... von Lee, Yoonhee, Cho, Bumhee, Cho, Nam Zin

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Nuclear reactor transient analysis via a quasi-static kinetics Monte Carlo method von YuGwon, Jo, Cho Bumhee, Cho Nam Zin

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A core design concept for multi-purpose research reactors von Seo, Chul Gyo, Cho, Nam Zin

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A practical method for accurate quantification of large fault trees von Choi, Jong Soo, Cho, Nam Zin

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ON SOME OUTSTANDING PROBLEMS IN NUCLEAR REACTOR ANALYSIS von Cho, Nam-Zin

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Global depletion analysis of Korean helium cooled solid breeder TBM model for demo fusion reactor von Yun, Sunghwan, Cho, Nam Zin, Ahn, Mu-Young, Cho, Seungyon

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Current status of design and analysis of Korean Helium-Cooled Solid Breeder Test Blanket Module von Cho, Seungyon, Ahn, Mu-Young, Kim, Duck Hoi, Lee, Eun-Seok, Yun, Sunghwan, Cho, Nam Zin, Jung, Ki Jung

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Depletion analysis of a solid-type blanket design for ITER von Yun, Sunghwan, Cho, Nam Zin, Ahn, Mu-Young, Cho, Seungyon

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Feasibility study of a dedicated nuclear desalination system: Low-pressure Inherent heat sink Nuclear Desalination plant (LIND) von Kim, Ho Sik, No, Hee Cheon, Jo, YuGwon, Wibisono, Andhika Feri, Park, Byung Ha, Choi, Jinyoung, Lee, Jeong Ik, Jeong, Yong Hoon, Cho, Nam Zin

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Preliminary safety analysis of Korea Helium Cooled Solid Breeder Test Blanket Module von Ahn, Mu-Young, Cho, Seungyon, Kim, Duck Hoi, Lee, Eun-Seok, Kim, Hyung-Seok, Suh, Jae-Seung, Yun, Sunghwan, Cho, Nam Zin

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MONTE CARLO DEPLETION UNDER LEAKAGE-CORRECTED CRITICAL SPECTRUM VIA ALBEDO SEARCH von Yun, Sung-Hwan, Cho, Nam-Zin

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Analytic Function Expansion Nodal (AFEN) Method in Hexagonal-Z Three-Dimensional Geometry for Neutron Diffusion Calculation von CHO, Nam Zin, LEE, Jaejun

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MONTE CARLO METHOD EXTENDED TO HEAT TRANSFER PROBLEMS WITH NON-CONSTANT TEMPERATURE AND CONVECTION BOUNDARY CONDITIONS von Cho, Bum-Hee, Cho, Nam-Zin

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A nonoverlapping local/global iterative method with 2-D/1-D fusion transport kernel and p-CMFD wrapper for transient reactor analysis von Cho, Bumhee, Cho, Nam Zin

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SOME OUTSTANDING PROBLEMS IN NEUTRON TRANSPORT COMPUTATION von Cho, Nam-Zin, Chang, Jong-Hwa

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AFEN method and its solutions of the hexagonal three-dimensional VVER-1000 benchmark problem von Lee, Jaejun, Cho, Nam Zin

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