Thermal-structural analysis considering contact stress between KO HCCR TBM sub-modules for ITER

Author

Kyu In Shin ; Dong Won Lee ; Hyung Gon Jin ; Eo Hwak Lee ; Suk-Kwon Kim ; Jae Sung Yoon ; Mu-Young Ahn ; Seungyon Cho

Author_Institution

Korea Atomic Energy Res. Inst., Daejeon, South Korea

fYear

2013

Firstpage

1

Lastpage

4

Abstract

The KO HCCR TBM (Korean Helium Cooled Ceramic Reflector Test Blanket Module) was consisted of 4 sub-modules. A thermal-structural analysis of the changed FW design, which has a 15 × 11 rectangular U-shape, was carried out according to the RCC-MR code considered the design pressure (10 MPa) and thermal stress results based on the thermal-hydraulic analysis. The contact stress between the TBM sub-modules was also evaluated to confirm the structural integrity. The results showed that the design requirements were satisfied.

Keywords

Tokamak devices; fusion reactor design; plasma pressure; plasma toroidal confinement; plasma-wall interactions; ITER; KO HCCR TBM submodules; Korean helium cooled ceramic reflector test blanket module; RCC-MR code; contact stress; plasma facing components; reactor design pressure; reactor structural integrity; rectangular U-shape first wall design; thermal stress; thermal-hydraulic analysis; thermal-structural analysis; Contacts; Finite element analysis; Plasma temperature; Stress; Temperature distribution; Thermal analysis; Thermal stresses; Contact stress; ITER; RCC-MR code; TBM; Thermal-structural analysis;

fLanguage

English

Publisher

ieee

Conference_Titel

Fusion Engineering (SOFE), 2013 IEEE 25th Symposium on

Conference_Location

San Francisco, CA

Print_ISBN

978-1-4799-0169-2

Type

conf

DOI

10.1109/SOFE.2013.6635424

Filename

6635424