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内容記述 |
This study presents a preliminary structural design of the water-cooled ceramic breeder (WCCB) Test Blanket Module (TBM)-set, proposed by the Institutes for Quantum Science and Technology in Japan, which is intended for installation in ITER's equatorial port No. 18. The research investigates the local tritium breeding ratio (TBR), the temperature distribution of the submodule, and the structural integrity assessment of the WCCB TBM-set under the ITER load environment to complete the review of the preliminary design activities. Numerical analyses, including nuclear and finite element analyses, are utilized to evaluate local TBR, temperature distribution, electromagnetic (EM) forces, load combinations, and stress performance. The results indicate that three cooling capacity enhancement structures are necessary to improve cooling capacity in the multiplier pebble bed area while maintaining the current local TBR. The EM analysis demonstrates that a Maxwell force will constantly act on the WCCB TBM-set, regardless of normal operation or plasma disruption, primarily due to the use of ferromagnetic materials. Furthermore, the structural integrity of the supporter, which provides mechanical support for the TBM and the shield in the WCCB TBM-set, is evaluated under load combinations. Although the current performance of the supporter is inadequate, design modifications may enable it to meet the criteria outlined in RCC-MRx. |
