Preliminary analysis of three ULOFAs based on the dual-functional lithium lead test blanket module configuration in ITER

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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 lithiumlead( 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.

Original languageEnglish
Title of host publication18th International Conference on Nuclear Engineering, ICONE18
Pages553-557
Number of pages5
DOIs
StatePublished - 2010
Event18th International Conference on Nuclear Engineering, ICONE18 - Xi'an, China
Duration: 17 May 201021 May 2010

Publication series

NameInternational Conference on Nuclear Engineering, Proceedings, ICONE
Volume6

Conference

Conference18th International Conference on Nuclear Engineering, ICONE18
Country/TerritoryChina
CityXi'an
Period17/05/1021/05/10

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