Contact Stress Evaluation Based on Thermal-Structural Analysis in KO HCCR TBM Submodules 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

Nucl. Fusion Dev. Center, Korea Atomic Energy Res. Inst., Daejeon, South Korea

Volume

42

Issue

6

fYear

2014

fDate

Jun-14

Firstpage

1807

Lastpage

1810

Abstract

The Korean Helium Cooled Ceramic Reflector Test Blanket Module (TBM) consisted of four submodules for International Thermonuclear Experimental Reactor program. The thermal-structural analysis considered a design pressure (10 MPa) and a thermal stress in the changed first wall design, which has a 15 mm × 11 mm rectangular U-shape, was carried out according to the RCC-MR code. The contact stress between the TBM submodules was also evaluated to confirm the structural integrity. The results showed that the design requirements were satisfied.

Keywords

Tokamak devices; fusion reactor blankets; fusion reactor design; plasma toroidal confinement; ITER; International Thermonuclear Experimental Reactor program; KO HCCR TBM Submodules; Korean Helium Cooled Ceramic Reflector Test Blanket Module; RCC-MR code; TBM submodules; contact stress evaluation; design pressure; first wall design; rectangular U-shape; structural integrity; thermal-structural analysis; Ceramics; Contacts; Helium; Stress; Temperature distribution; Thermal analysis; Thermal stresses; Allowable stress ( (S_{m}) ); Allowable stress (Sm); International Thermonuclear Experimental Reactor (ITER); RCC-MR code; TBM; Tresca stress; Tresca stress.; contact stress; thermal-structural analysis;

fLanguage

English

Journal_Title

Plasma Science, IEEE Transactions on

Publisher

ieee

ISSN

0093-3813

Type

jour

DOI

10.1109/TPS.2014.2314473

Filename

6810169