Author:
Jhung Myung Jo,Kim Seok Hun,Choi Young Hwan,Jung Sunggyu,Kim Jong Min,Kim Ji Ho,Kim Jong Wook,Jang Changheui,Chang Yoon Suk,Kang Ki Sig
Publisher
Springer Science and Business Media LLC
Subject
Mechanical Engineering,Mechanics of Materials
Reference11 articles.
1. IAEA, Guidelines on pressurized thermal shock analysis for WWER nuclear power plants, IAEAEBP-WWER-08, Rev.1, International Atomic Energy Agency, Vienna, (2005).
2. J. Sievers and B. R. Bass, Comparative assessment of project FALSIRE — results, Nuclear Engineering and Design, 152 (1994) 19–37.
3. B. R. Bass, C. E. Pugh, J. Sievers and H. Schulz, Overview of the International Comparative Assessment Study of Pressurized Thermal Shock in Reactor Pressure Vessels (RPV PTS ICAS), The International Journal of Pressure Vessels and Piping, 78 (2001) 197–211.
4. C. Faidy, PROSIR — Probabilistic Structural Integrity of a PWR Reactor Pressure Vessel, Proposed to OECD/NEA PWG3 — Metal Group, EDF-SEPTEN, (2003).
5. D. P. G Lidbury, A. H. Sherry, B. R. Bass, P. Gilles, D. Connors, U. Eisele, E. Keim, H. Keinanen, K. Wallin, D. Lauerova, S. Marie, G. Nagel, K.-F. Nilsson, D. Siegele and Y. Wadier, Validation of Constraint-Based Methodology in Structural Integrity of Ferritic Steels for Nuclear Reactor Pressure Vessels, Fatigue and Fracture of Engineering Materials and Structures, 29 (2006) 1–21.
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