DNBR CALCULATION IN CORE DURING COOLANT PUMP ROTOR SEIZURE ACCIDENT FOR QINSHAN NUCLEAR POWER PLANE
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Graphical Abstract
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Abstract
DNBR of the hot fuel assembly in core is calculated by use of the subchannel analysis code THAS-PC1 for the coolant pump rotor seizure accident. The results show that DNBR calculated by W--3,BAW--2 and CONDIE correlations agree with the values of CHF table. They reach the minimum DNBRwhen the transient time is equal to 2 seconds, and the minimum DNBR fall below limiting value 1.3.The DNBR calculated by BIASI correlation is much higher and far greater than the limit value 1.3.
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