Abstract
Based on the PWR best estimate program RELAP5/MOD3.3, the reactor coolant system and the passive core cooling system of AP1000 Nuclear Power Plant were modeled and analyzed. Some key transient parameters were obtained, including RCS pressure, break discharge, etc. The result is in close agreement with the result generated by NOTRUMP code from Westinghouse (USA). The calculation results show that safeguard system of APl000 can effectively reduce the pressure of the first loop, also can prevent core uncovered. The safety of AP1000 during a small break Loss of Coolant Accident caused by DVI line breaking is verified.
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