NDLI: The Analysis of AP1000 Beyond Design Basis DEDVI Accident

Content Provider	The American Society of Mechanical Engineers (ASME) Digital Collection
Author	Zhu, Sheng
Copyright Year	2013
Abstract	Double ended break of direct vessel injection line (DEDVI) is the most typical small-break lost of coolant accident (LOCA) in AP 1000 nuclear power plant. This study simulated the DEDVI (without actuation of automatic depressurization system 1–3 stage valves, accumulators and passive residual heat removal heat exchanger) beyond design basis accident (BDBA) to validate the safety capability of AP1000 under such conditions. The results show that the core will be uncovered for about 863 seconds and then recovered by water after gravity injection from IRWST into the pressure vessel. The peak cladding temperature (PCT) goes up to 838.08°C, much lower than the limiting value 1204°C. This study confirms that in the DEDVI beyond design basis accident, the passive core cooling system (PXS) can effectually cool the core and preserve it integrate, and ensure the safety of AP 1000 nuclear power plant.
Sponsorship	Nuclear Engineering Division
File Format	PDF
ISBN	9780791855836
DOI	10.1115/ICONE21-15140
Volume Number	Volume 6: Beyond Design Basis Events; Student Paper Competition
Conference Proceedings	2013 21st International Conference on Nuclear Engineering
Language	English
Publisher Date	2013-07-29
Publisher Place	Chengdu, China
Access Restriction	Subscribed
Subject Keyword	Water Temperature Gravity (force) Vessels Cooling systems Valves Heat exchangers Secondary cells Design Heat Pressure vessels Coolants Safety Nuclear power stations Cladding systems (building) Accidents
Content Type	Text
Resource Type	Article

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