Numerical analysis on ingress of coolant event in test blanket module for ITER based on two-fluid model

The numerical safety analyses on an ingress of coolant event (ICE) in the test blanket module have been performed using the modified TRAC-PF1 code based on the two-fluid model to clarify safety characteristics for Water-Cooled Ceramic Breeder Test Blanket Module (WCCB-TBM) developed in Japan. Using the WCCB-TBM nuclear, thermal and mechanical functional tests of the blanket will be examined in the International Thermonuclear Experimental Reactor (ITER). The modified TRAC-PF1 code includes the chemical reaction model between beryllium and water and the heat transfer model between coolant and packed bed in the TBM. This paper describes the predicted results for ICE, such as mass flow rate, void fraction, pressure and temperature transients in coolant, transient temperature distribution in the packed bed and amount of the heat and H_2 generation with chemical reaction between beryllium and water.