Study and calculation of the progress of serious failures and heat transmission at the bottom of nuclear reactor VVER-1000

Study and calculation of the progress of serious failures and heat transmission at the bottom of nuclear reactor VVER-1000

Dr. Tran Chi Thanh; Eng. Pham Ngoc Tuyen; Eng. Nguyen Tan Nghia; Eng. Nguyen Van Thao; Eng. Hoang Tiep – Institute of Energy, Ministry of Industry and Trade

Abstract.
The paper introduces the progress of failure in the Russian VVER nuclear reactor and calculates the heat transmission of the fused fuel and material basin in the bottom of the reactor tank in several serious failure scenarios, using effective convection model. The simulation results show that the heat interaction from the fuel and material basin may lead to high-temperation creep of the reactor wall after a few hours. The effectiveness of some cooling methods applied in case of serious failures is also calculated and analyzed.

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