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Preliminary Analysis of Three ULOFAs Based on the Dual-Functional Lithium Lead Test Blanket Module Configuration in ITER

[+] Author Affiliations
Weifeng Ni, Suizheng Qiu, Guanghui Su, Wenxi Tian

Xi’an Jiaotong University, Xi’an, China

Paper No. ICONE18-29586, pp. 553-557; 5 pages
doi:10.1115/ICONE18-29586
From:
  • 18th International Conference on Nuclear Engineering
  • 18th International Conference on Nuclear Engineering: Volume 6
  • Xi’an, China, May 17–21, 2010
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 978-0-7918-4934-7
  • Copyright © 2010 by ASME

abstract

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.

Copyright © 2010 by ASME
Topics: Lithium

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