References
- IAEA, Safety Assessment and Verification of Nuclear Power Plants, Safety Standard Series, 2002. No. NS-G-1.2.
- Y.H. Seo, Won Sang Jeong, Young Tea Moon, Equipment survivability assessment in APR1400, Korea Nucl. Soc. (2012) 731.
- S.I. Lee, H.K. Jung, Development of the NPP instrument requirements for highly survivability under severe accidents, in: Conference on Korea Society for Energy Engineering, 2013, 121-121.
- R. Lin, Z. Wang, Y. Sun, Wireless sensor network solutions for real time monitoring of nuclear power plant, in: Proceedings of the 5th World Congress on Intelligent Control and Automation, June 2004. HangZhou, China.
- IEEE, IEEE standard for qualifying class 1E equipment for nuclear power generating station, IEEE Std (1973), 323-1974.
- IEEE, IEEE standard for qualifying class 1E equipment for nuclear power generating station, IEEE Std (2003), 323-2003.
- IEEE, IEEE standard for seismic qualification of equipment for nuclear power generating stations, IEEE Std (2013), 344-2013.
- IAEA, Assessment of nuclear power plant equipment reliability performance for severe accident condition, TECDOCDD 1135.
- D.H. Kim, Y.S. Park, Severe Accident Mitigation Design in APR+ Nuclear Power Plant, Korea Society for Energy Engineering, 2013.
- USNRC, 10CFR50.34(f), Additional TMI-related Requirements, 2009.
- USNRC, SECY-90-016, Evolutionary Light-Water Reactor Certification Issues and Their Relationship to Current Regulatory Requirements, 1990.
- USNRC, SECY 93-9087, Policy Technical and Licensing Issues Pertaining to Evolutionary and Advanced Light Water Reactor Design, 1993.
- Pacific Northwest National Laboratory, PNNL-24198, Light Water Reactor Sustainability Program-Assessment of Cable Aging Equipment, Status of Acquired Materials, and Experimental Matrix at the Pacific Northwest National Laboratory, 2015.
- EPRI, Plant Support Engineering: Elastomer Handbook for Nuclear Power Plants, 1014800, 2007.
- KIMM, Development of Emerging Core Technique of Equipment Qualification on Design Based Events and Severe Accidents of NPPs, TR-2016-195, 2016.
- R.K. Weese, A.K. Burnham, H.C. Tuner, T.D. Tran, Physical characterization of RX-55-AE-5 a formulation of 97.5% 2,6-diamino-3,5-dinitropyrazine-1-oxide (LLM-105) and 2.5% Viton A, in: North American Thermal Analysis Society 33rd Annual Conference, 2005.
- F.P. Incropera, D.P. Dewitt, T.L. Bergman, A.S. Lavine, Fundamentals of Heat and Mass Transfer, Wiley, 1981.
- S.W. Churchill, W. Bernstein, A correlating equation for forced convection from gases and liquid to a circular cylinder in crossflow, J. Heat Transfer ASME (1977).
- C. Lee, K.Y Kim, B.H. Ryu, K.J. Lim, Evaluation of radiation degradation of crosslinked polyethylene using TGA, J. KIIS, (2003).
- KAERI, Accelerated ageing test of cable materials used in nuclear power plants for the evaluation of lifetime, KAERI/TR-2424, (2003).