Based on the structural design of the Chinese ITER Dual Functional Lithium-Lead Test Blanket Module (DFLL-TBM), Three Unprotected Loss of Flow Accidents (ULOFAs) were investigated preliminarily, assuming that the whole nuclear heat in TBM was carried away by the flowing lithium-lead (LiPb). The results show that the temperature of the first wall (FW) increases rapidly and the maximum temperature appears at the lower part of FW. In the analysis of ULOFAs, the maximum temperature might exceed the melting point of structure material steel. This event must be avoided by the fusion power shutdown system that terminates plasma burn.
- Nuclear Engineering Division
Preliminary Analysis of Three ULOFAs Based on the Dual-Functional Lithium Lead Test Blanket Module Configuration in ITER
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Ni, W, Qiu, S, Su, G, & Tian, W. "Preliminary Analysis of Three ULOFAs Based on the Dual-Functional Lithium Lead Test Blanket Module Configuration in ITER." Proceedings of the 18th International Conference on Nuclear Engineering. 18th International Conference on Nuclear Engineering: Volume 6. Xi’an, China. May 17–21, 2010. pp. 553-557. ASME. https://doi.org/10.1115/ICONE18-29586
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