1 김종성, "중성자 조사에 따른 오스테나이트 스테인리스 강의 기계적 재료거동 변화를 고려한 사용자 정의 보조 프로그램 개발" 대한기계학회 37 (37): 1127-1132, 2013
2 Kim, J.S., "Susceptibility Assessment of Irradiation-Assisted Stress Corrosion Cracking on Lower Core Plate in Pressurized Water Reactor Internals" 2013
3 KHNP, "Periodic Safety Review Report of Unit A"
4 Rice, J.R., "On the Ductile Enlargement of Voids in Triaxial Stress Fields" 17 : 201-217, 1969
5 Baso, Y, "On Fracture Locus in the Equivalnet Strain and Stress Triaxiality Space" 46 : 81-98, 2004
6 ASME, "Materials,”ASME B&PV, Sec.II, Part D"
7 EPRI, "Material Reliability Program: PWR Internals Age-Related Material Properties, Degradation Mechanisms, Models, and Basis Data State of Knowledge (MRP-211), 1015013"
8 EPRI, "Material Reliability Program: Functionality Analysis for Westinghouse and Combustion Engineering Representative PWR Internals (MRP-230, Rev.2), 1021026"
9 EPRI, "Material Reliability Program: Development of Material Constitutive Model for Irradiated Austenitic Stainless Steels (MRP-135-Rev.1), 1020958"
10 USNRC, "Generic Aging Lessons Learned (GALL) Report" 2010
1 김종성, "중성자 조사에 따른 오스테나이트 스테인리스 강의 기계적 재료거동 변화를 고려한 사용자 정의 보조 프로그램 개발" 대한기계학회 37 (37): 1127-1132, 2013
2 Kim, J.S., "Susceptibility Assessment of Irradiation-Assisted Stress Corrosion Cracking on Lower Core Plate in Pressurized Water Reactor Internals" 2013
3 KHNP, "Periodic Safety Review Report of Unit A"
4 Rice, J.R., "On the Ductile Enlargement of Voids in Triaxial Stress Fields" 17 : 201-217, 1969
5 Baso, Y, "On Fracture Locus in the Equivalnet Strain and Stress Triaxiality Space" 46 : 81-98, 2004
6 ASME, "Materials,”ASME B&PV, Sec.II, Part D"
7 EPRI, "Material Reliability Program: PWR Internals Age-Related Material Properties, Degradation Mechanisms, Models, and Basis Data State of Knowledge (MRP-211), 1015013"
8 EPRI, "Material Reliability Program: Functionality Analysis for Westinghouse and Combustion Engineering Representative PWR Internals (MRP-230, Rev.2), 1021026"
9 EPRI, "Material Reliability Program: Development of Material Constitutive Model for Irradiated Austenitic Stainless Steels (MRP-135-Rev.1), 1020958"
10 USNRC, "Generic Aging Lessons Learned (GALL) Report" 2010
11 Jeon, J.Y., "Effect of Thermal Aging of CF8M on Multi-Axial Ductility and Application to Fracture Toughness Prediction" 38 (38): 1466-1477, 2015
12 Westinghouse, "Design Report of Unit A Reactor Pressure Vessel Internals Components for Continued Operation" 2007
13 KHNP, "Database for Reactor Internals in Domestic Operating Nuclear Power Plants"
14 MSC, "ANSYS User’s Guide, Ver.12.1"
15 Simulia, "ABAQUS User's Manuals, Ver.6.11-1"