Analysis of BWR long-term station blackout accident using TRAC-BF1

A long-term station blackout accident of a BWR is analysed using TRAC-BF1, and the calculated results are compared with the observed data at the unit 2 reactor of the Fukushima Daiichi nuclear power plant. The RCIC is assumed to be actuated, and the reactor pressure and the liquid level in the core are found to be stable and the dry well pressure increases gradually. The effects of leakage and heat release from the containment are discussed. The reactor pressure increases to the SRV set point and the liquid level and the dry well pressure decrease after the termination of RCIC. The calculated results are in good agreement with the observed data, and the thermal–hydraulic transient of unit 2 reactor is shown to be simulated well.

► A long-term station blackout accident of a BWR is analysed using TRAC-BF1.
► The results are in good agreement with the data at Fukushima Daiichi unit 2.
► The effects of leakage and heat release from the containment are discussed.