Design and thermal performance of an improved mechanically attached module for divertor plate of LHD

Fusion Engineering and Design

Volumn 75-79, Issue SUPPL., 2005, Pages 297-301

  Kubota, Y ^a,c   Masuzaki, S ^a   Morisaki, T ^a   Tokunaga, K ^b   Noda, N ^a  

^a NATIONAL INSTITUTE FOR FUSION SCIENCE   (Japan)

^b KYUSHU UNIVERSITY   (Japan)

^c NONE   (Japan)

Author keywords

ACT; Armor tile; Divertor plate; Graphite; High heat flux; LHD; Outgassing

Indexed keywords

BOLTS; DEGASSING; FUSION REACTOR DIVERTORS; GRAPHITE; HEAT SINKS; SHEAR DEFORMATION; SHEET METAL; STAINLESS STEEL; STRUCTURAL DESIGN; THERMOANALYSIS;

ACT; ARMOR TILES; DIVERTOR PLATES; HIGH HEAT FLUX; LARGE HELICAL DEVICE (LHD);

PLATES (STRUCTURAL COMPONENTS);

EID: 27844463541     PISSN: 09203796     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.fusengdes.2005.06.320     Document Type: Article

References (7)

1. M. Lipa Development and heat flux testing of separate first wall concept for NET/ITER Fusion Technol. 1 1992 307 311
2. P. Zaccaria, S. Dal Bello, and D. Marcuzzi Test and analyses for the mechanical and thermal qualification of the new RFX first tiles Fusion Eng. Des. 66-68 2003 289 293
3. N. Noda, R. Sakamoto, Y. Kubota, A. Sagara, S. Masuzaki, and O. Motojima LHD helical divertor and its performance in the first experiment J. Plasma Fusion Res. Ser. 3 2000 180 183
4. O. Motojima, K. Akaishi, K. Fujii, S. Fujiwaka, S. Imagawa, and H. Ji Physics and engineering design studies on the large helical device Fusion Eng. Des. 20 1993 3 14
5. A. Iiyoshi, A. Komori, A. Ejiri, M. Emoto, H. Funaba, and M. Goto Overview of the large helical device project Nucl. Fusion 39 1999 1245 1255
6. Y. Kubota, N. Noda, A. Sagara, N. Inoue, K. Akaishi, and O. Motojima Electron beam test facility for research and development of plasma feeing components NIFS Intern. Rep. NIFS-MEMO 13 1994
7. Y. Kubota, N. Noda, A. Sagara, R. Sakamoto, K. Yamazaki, and T. Satow Thermal performance and 3D analysis of advanced mechanically joined divertor plate for LHD under steady state high heat flux Fusion Eng. Des. 56-57 2001 205 210