Recent R&D activities on plasma facing components at JAERI

Author

Sato, K. ; Suzuki, S. ; Araki, M. ; Nakamura, K. ; Watanabe, K. ; Yokoyama, K. ; Dairaku, M. ; Okumura, Y. ; Ohara, Yuki ; Akiba, M.

Author_Institution

JAERI, Ibaraki, Japan

Volume

1

fYear

1995

fDate

30 Sep-5 Oct 1995

Firstpage

220

Abstract

Plasma Facing Components will be exposed to severe heat loads during the normal operation, and will severely be eroded by evaporation and particle emission during disruptions in next generation fusion devices such as International Thermonuclear Experimental Reactor (ITER). In this paper, we present recent major R&D topics on plasma facing components (PFCs) at JAERI as follows; (1) thermal cycling experiments on a 1 m long divertor mock-up, (2) disruption simulation tests on B₄C doped CFCs and tungsten, (3) tensile and bending tests of beryllium/copper alloy duplex structures

Keywords

fusion reactor materials; fusion reactor safety; plasma instability; plasma-wall interactions; B₄C doped CFCs; Be; Be/Cu alloy duplex structures; Cu; ITER; International Thermonuclear Experimental Reactor; JAERI; PFC; W; bending tests; disruption simulation tests; disruptions; divertor mock-up; erosion; evaporation; next generation fusion devices; particle emission; plasma facing components; severe heat loads; tensile tests; thermal cycling; Coolants; Cooling; Plasma temperature; Research and development; Steady-state; Temperature distribution; Testing; Thermal conductivity; Thermal stresses; Tiles;

fLanguage

English

Publisher

ieee

Conference_Titel

Fusion Engineering, 1995. SOFE '95. Seeking a New Energy Era., 16th IEEE/NPSS Symposium

Conference_Location

Champaign, IL

Print_ISBN

0-7803-2969-4

Type

conf

DOI

10.1109/FUSION.1995.534207

Filename

534207