SNURPL

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57	An Adaptive Scheme to Minimize Feed Fuel Assembly Enrichment in Reload Cycle Core Design of PWR Tong Kyu Park, Han Gyu Joo, Chang Hyo Kim	Detail
56	Examination of Temperature Dependent Subgroup Formulations in Direct Whole Core Transport Calculation for Power Reactors Yeon Sang Jung, Un Chul Lee, Han Gyu Joo	Detail
55	Multi-Group Extension of Unified Nodal Method Tae Young Han, Hyun Chul Lee, Han Gyu Joo, Chang Hyo Kim	Detail
54	GENERATION OF SUBGROUP WEIGHTS EMPLOYING SHIELDED CROSS SECTION CONSERVATION PRINCIPLE FOR REPRESENTATIVE PIN CELLS Lenoid Pogosbekyan, Han Gyu Joo, Chang Hyo Kim, Kang Seok Kim	Detail
53	Two-Dimensional Semi-Analytic Nodal Method for Multigroup Pin Power Reconstruction Seung Gyou Baek, Han Gyu Joo, Un Chul Lee	Detail
52	Sub-Plane Scheme for a Radial Transport and Axial Diffusion Code Jin-Young Cho, Kang-Seog Kim, and Chung-Chan Lee, Han Gyu Joo	Detail
51	Two-group CMFD accelerated multi-group calculation with a semi-analytic nodal kernel Tae Young Han, Han Gyu Joo, Chang Hyo Kim	Detail
50	Assembly based modular ray tracing and CMFD acceleration for BWR cores with different fuel lattices J. W. Thomas, H. G. Joo, Y. Xu, B. Kochunas and T. J. Thomas	Detail
49	THE NUMERICAL NUCLEAR REACTOR – A HIGH FIDELITY, INTEGRATED NEUTRONIC, THERMAL-HYDRAULIC AND THERMO-MECHANICAL CODE D. P. Weber, T. Sofu, P. Pfeiffer, W. S. Yang, K. S. Kim, T. H. Chun, T. Downar, J. Thomas, Z. Zhong and H.G. Kim and C.H Kim	Detail
48	DEPLETION CAPABILITY OF THE 3-DIMENSIONAL WHOLE CORE TRANSPORT CODE DeCART Kang-Seog Kim, Jin Young Cho, Sung Quun Zee, Ho Jin Park, Han Gyu Joo, Chang Hyo Kim	Detail