Station Blackout Accident for the Korea Nuclear Unit 1 Using RELAP5/MOD1
A station blackout accident which occured at the Korea Nuclear Unit 1 (KNU-1) at the Kori site in Korea on June 9, 1981 was analyzed by using the RELAP5/MOD1 code.
The incident was occured at 11:05 a. m. due to the malfunction of a steam generator level guage. The false level signal eventually caused the reactor and turbine trip. Following the turbine trip, the excitor of the generator remained functioning and the reactor coolant pumps remained connected to the internal source for 30 seconds, thus providing full reactor coolant flow for 30 seconds after the reactor trip. Upon the loss of the generator power, one of two buses failed to automatically transfer to the off-site power and the other also failed in 30 seconds after generator trip. The transfer to the off-site power was restored in about 26 minutes. During the blackout period two diesel generators provided the necessary electrical power to the corresponding instruments and two motor-driven auxiliary feedwater pumps.
To confirm that the adequate core cooling was maintained by natural circulation during the blackout accident for KNU-1
To establish the sequence of events which occured during the transient
To assess the capability of the RELAP5/MOD1 code in predicting the plant transient
To verify the modeling technique for a two-loop pressurized water reactor(PWR) by using RELAP5/MOD1 code
KeywordsSteam Generator Natural Circulation Reactor Coolant Decay Heat Reactor Coolant System
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