1. Design characteristics of the advanced power reactor 1400;Kim,2009
2. Proceedings of the CSNI Workshop on Structural Reliability Evaluation and Mechanical Probabilistic Approaches of NPP Components, NEA/CSNI/R(2007)18;OECD/NEA,2008
3. Pressurized Thermal Shock in Nuclear Power Plants: Good Practices for Assessment, IAEA-TECDOC-1627;IAEA,2010
4. A-Pro2: Phase 2 ASINCO Project for Probabilistic Fracture Mechanics Analysis – Korea Results, KINS/RR-1483;KINS,2016
5. An Assessment of the Integrity of the PWR Pressure Vessels, Second Report by a Study Group under the Chairmanship of Dr. W. Marshall, United Kingdom Atomic Energy Authority;UKAEA,1982