References
- INCOSE Systems Engineering Handbook v. 3.2.2 INCOSE-TP-2003-002-03.2.2 October 2011.
- Avinash J. Gaikwad, P. K. Vijayan, Sharad Bhartya, Kannan Iyer, Rajesh Kumar, A. D. Contractor, H. G. Lele, S. F. Vhora, A. K. Maurya, A. K. Ghosh, and H. S. Kushwaha, Effect of Coolant Inventories and Parallel Loop Interconnections on the Natural Circulation in Various Heat Transport Systems of a Nuclear Power Plant during Station Blackout, Research Article ID 458316, 2008.
- Nuclear Energy Institute (NEI 12-06), Rev. 0, Diverse And Flexible Coping Strategies (FLEX) Implementation Guide August 2012.
- Sang-Won Lee, Tae Hyub Hong, Mi-Ro Seo, Young-Seung Lee, and Hyeong-Taek Kim, Extended Station Blackout Coping Capabilities of APR1400, Research Article ID 980418, 2014.
- Jongrok Hwang, and Seungjong Oh, Developing Optimal Procedure of Emergency Outside Cooling Water Injection for APR1400 Extended SBO Scenario Using MARS Code, KEPCO International Nuclear Graduate School, 1456-1 Shinam-ri, Seosaeng-myeon, Uljugun, Ulsan, Korea, 2013.
- APR1400 Standard Safety Analysis Report (SSAR).
- Alexander Kossiakoff, William N. Sweet, Samuel j. Seymour, and Steven M. Biemer, Systems Engineering Principles and Practice, Second Edition, 2011.
- Systems Engineering Handbook, a Guide for System Life Cycle Processes and activities, Fourth Edition, Incose-tp-2003-002-04, 2015.
- APR1400 Design Description, 2014 Korea Hydro& Nuclear Power Co., Ltd.
- IAEA Website, https://www.iaea.org/pris/.
- Sang Ho Kim, Soon Heung Chang, Yu Jung Choi, and Yong Hoon Jeong, A Passive Decay Heat Removal Strategy of The Integrated Passive Safety System (IPSS) for SBO Combined with LOCA, Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, 291, Daehak-ro, Yuseong-gu, Daejeon 34141, Republic of Korea, 13 November 2015.
- Carneiro, Paulo, 2013. Brazilian nuclear operator's response to Fukushima accident, IAEA Technical Meeting on Evaluation of NPP Design Safety in the Aftermath of the Fukushima Daiichi Accident, 26-29 August 2013, Vienna International Centre.
- APR1400 Design Document Tier 2, Probabilistic Risk Assessment and Severe Accident Evaluation, Kepco and KHNP Co., Ltd., Revision 0, December 2014.
- Passive Safety Systems and Natural Circulation in Water Cooled Nuclear Power Plants, IAEA-TECDOC-1624, IAEA, Vienna, 2009.