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Also, a fuzzy neural network (FNN) is designed to estimate the break size.
The critical break size of crack unstable tearing is calculated by the EPFM method.
The sequence analyzed corresponded to a medium-break loss-of-coolant accident with a break size of 3 in.
The influence of the break location and break size on the safety performance of SCWR-M is also concluded.
The present paper is focused on test 6-1 that simulated a RPV upper head SBLOCA with a break size equivalent to 1.9% cold leg break.
Based on the thermal hydraulics results regarding new break size boundaries and new success criteria, five new event trees (ETs) were developed.
Similar(47)
Different scenarios due to break sizes and plasma shutdown conditions are taken into account.
The influences of different break sizes during these accidents are comprehensively analyzed.
Three different break sizes are analyzed to clarify the hot and cold LOCA characteristics of the SCWR-M.
Four tests were performed simulating break sizes of 0.2 2% (approximately corresponding to 1.25 4″ breaks for a referenced nuclear power plant) at cold-leg for assessing the PCCS capability in accident management.
Regarding the In-Box LOCA, the influences of different break sizes and locations are thoroughly analyzed based on a relatively accurate modeling method of the heat structures in sub-modules.
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