1 M. Kojic, "The effective stress function algorithm for thermo-elasto-plasticity and creep" 24 (24): 1509-1532, 1987
2 Y. B. Yang, "Solution strategy and rigid element for nonlinear analysis of elastically structures based on updated Lagrangian formulationk" 29 (29): 1189-1200, 2007
3 J. M. Winget, "Solution algorithms for nonlinear transient heat conduction analysis employing element-by-element iterative strategies" 52 (52): 711-815, 1985
4 C. Vitanza, "RIA failure threshold and LOCA limit at high burn-up" 43 (43): 1074-1079, 2006
5 P. G. Hodge, "Plastic analysis of structures" RE Krieger Publishing Company 1981
6 "PIAnO User’s Manual Version 3. 5"
7 N. E. Todreas, "Nuclear systems" CRC Press 2010
8 M. Suzuki, "Light Water Reactor Fuel Analysis Code FEMAXI-IV(Ver.2)"
9 M. Ichikawa, "LWR fuel safety research with particular emphasis on RIA/LOCA and other conditions" 26 (26): 118-125, 1989
10 J. R. Lamarsh, "Introduction to nuclear engineering" Prentice hall 2001
1 M. Kojic, "The effective stress function algorithm for thermo-elasto-plasticity and creep" 24 (24): 1509-1532, 1987
2 Y. B. Yang, "Solution strategy and rigid element for nonlinear analysis of elastically structures based on updated Lagrangian formulationk" 29 (29): 1189-1200, 2007
3 J. M. Winget, "Solution algorithms for nonlinear transient heat conduction analysis employing element-by-element iterative strategies" 52 (52): 711-815, 1985
4 C. Vitanza, "RIA failure threshold and LOCA limit at high burn-up" 43 (43): 1074-1079, 2006
5 P. G. Hodge, "Plastic analysis of structures" RE Krieger Publishing Company 1981
6 "PIAnO User’s Manual Version 3. 5"
7 N. E. Todreas, "Nuclear systems" CRC Press 2010
8 M. Suzuki, "Light Water Reactor Fuel Analysis Code FEMAXI-IV(Ver.2)"
9 M. Ichikawa, "LWR fuel safety research with particular emphasis on RIA/LOCA and other conditions" 26 (26): 118-125, 1989
10 J. R. Lamarsh, "Introduction to nuclear engineering" Prentice hall 2001
11 김효찬, "Implementation of Effective-Stress-Function Algorithm for Nuclear Fuel Performance Code" 한국정밀공학회 14 (14): 791-796, 2013
12 N. Marchal, "Finite element simulation of Pellet-Cladding Interaction (PCI) in nuclear fuel rods" 45 (45): 821-826, 2009
13 Y. W. Rhee, "Fabrication of sintered annular fuel pellet for HANARO irradiation test" 47 (47): 345-350, 2010
14 ChangHwan Shin, "Evaluation of loss coefficient for an end plug with side holes in dual-cooled annular nuclear fuel" 대한기계학회 26 (26): 3119-3124, 2012
15 K. H. Han, "Development of a thermalhydraulic analysis code for annular fuel assemblies" 226 (226): 267-275, 2003