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内容記述 |
The Water-cooled ceramic breeder (WCCB) Test Blanket Module (TBM) is a key component for advancing fusion power generation in Japan. The WCCB TBM-set is a prototype for the DEMO breeding blanket (BB) and is slated for installation in ITER to demonstrate heat extraction and tritium self-sufficiency. A critical component, the submodule, utilizes a coolant resembling that of a pressurized water reactor (PWR), operating at 15.5 MPa and 300°C, circulating through internal containers and U-shaped pipes. To validate the design, a dedicated heat flux test facility was established at the National Institutes for Quantum Science and Technology in Japan. This facility, equipped with a 600 kW electron beam (EB) gun, simulates the plasma heat loads expected in ITER. Preliminary calibration of the facility was performed using a designed calorimeter, which successfully determined the EB parameters required to replicate the ITER's heat flux intensity. A Faraday cup was utilized to confirm a Gaussian beam profile with a diameter of 27.6 mm. During the tests, a non-destructive infrared (IR) camera was used to monitor the temperature of the mock-up's first wall (FW), with its measurements successfully calibrated against those from thermocouples. A 60-second heat flux test was conducted, and the post-test performance was evaluated using acceptance criteria from the ITER divertor. Results showed no signs of melting, defects, or coolant leaks, and no hot spots were observed. These findings confirm that the current WCCB TBM design, along with its fabrication and assembly methodologies, meets acceptable standards |
