Title :
Material behavior of JT-60U plasma facing components and installation of B4C-converted CFC/graphite tiles
Author :
Ando, T. ; Kodama, K. ; Matsukawa, M. ; Ouchi, Y. ; Arai, T. ; Yagyu, J. ; Kaminaga, A. ; Sasajima, T. ; Koike, T. ; Shimizu, M.
Author_Institution :
JAERI, Ibaraki, Japan
Abstract :
Wall damages of the JT-60U plasma facing components in the recent operation are more serious than in the previous one. Erosion of carbon fiber composite (CFC) divertor tiles due to field ripple of the toroidal coil is observed. Several bolt-loosening divertor tiles are eroded or disconnected. Mechanical fracture of CFC first wall tiles is found. The first application of B4C-converted CFC tiles (surface-boronized ones using conversion method) is also shown. The B 4C-converted tiles have been installed to the outboard striking zone of the divertor plate and in use satisfactorily in the high power heating divertor operation
Keywords :
boron compounds; carbon fibre reinforced composites; ceramics; fracture; fusion reactor materials; fusion reactor operation; fusion reactor safety; fusion reactors; graphite; wear; B4C; B4C-converted CFC/graphite tiles; C fiber divertor tiles; JT-60U plasma facing components; bolt-loosening divertor tiles; divertor plate; erosion; field ripple; first wall tiles; fusion reactor; high power heating divertor operation; material behavior; mechanical fracture; outboard striking zone; toroidal coil; wall damages; Cogeneration; Coils; Heating; Niobium; Plasma applications; Plasma materials processing; Plasma properties; Surface cracks; Surface discharges; Tiles;
Conference_Titel :
Fusion Engineering, 1993., 15th IEEE/NPSS Symposium on
Conference_Location :
Hyannis, MA
Print_ISBN :
0-7803-1412-3
DOI :
10.1109/FUSION.1993.518390
