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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.
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.
This paper presents the results which has been obtained for different SBLOCA break sizes with the best estimate TRACE V5.0 patch 2 thermal hydraulic code and their comparison with those obtained by Westinghouse with NOTRUMP code.
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.
Similar(52)
The critical break size of crack unstable tearing is calculated by the EPFM method.
Also, a fuzzy neural network (FNN) is designed to estimate the break size.
The influence of the break location and break size on the safety performance of SCWR-M is also concluded.
The sequence analyzed corresponded to a medium-break loss-of-coolant accident with a break size of 3 in.
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.
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