Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
4921491 | Fusion Engineering and Design | 2016 | 7 Pages |
Abstract
Using a conceptual design of the Korean helium cooled ceramic reflector (HCCR) test blanket module (TBM) including the TBM-shield for testing in ITER, a structural analysis with electro-magnetic (EM) loads is performed. From a previous analysis of the material magnetization due to the use of reduced activation ferritic-martensitic (RAFM) steel as the TBM structure material and EM analysis considering the major disruption of MD-I, MD-II, and MD-IV, the forces are obtained and used for the current structural analysis. The results indicate that the maximum stress occurs at the He purge line at the upper and lower region of the breeding zone (BZ) box including the graphite reflector region, which meets the design requirement. In addition, displacements are lower than the designed gaps from the TBM port plug (PP) frame. The results are provided to the load combination analysis.
Keywords
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Energy Engineering and Power Technology
Authors
Dong Won Lee, Seong Dae Park, Hyung Gon Jin, Eo Hwak Lee, Suk-Kwon Kim, Jae Sung Yoon, Kyu In Shin, Jai Hak Park, Youngmin Lee, Duck Young Ku, Seungyon Cho,