Article ID Journal Published Year Pages File Type
271181 Fusion Engineering and Design 2014 6 Pages PDF
Abstract

Korea has developed a helium cooled ceramic reflector (HCCR) test blanket module (TBM) consisting of four sub-modules in an ITER. From the draft design of the side wall (SW) according to a thermal-hydraulic analysis, a mechanical analysis was performed considering a design channel pressure of 10 MPa. The SW comprised of sixteen grids with the seventeen partitions for the manifold function satisfied 1.5Sm of the allowable stress (Sm) according to RCC-MR code at the maximum stress region in the SW. In addition, an elastic analysis of the draft design of the back manifold (BM) was carried out, which supported the four sub-modules in the HCCR TBM and has the main inlet/outlet of the He cooling pipe, the measurement pipes, and He purge gas lines from the port cell. The results show that the maximum stress was higher than 1.5Sm, and the BM design has been modified to satisfy the BM function and requirements.

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