Published July 2006 | Version v1
Journal article

An examination into weldability of irradiated material by a laser welding method for repair of ITER blanket

  • 1. Kawasaki Plant Systems, Ltd., Tokyo (Japan)
  • 2. Japan Atomic Energy Agency, Fusion Research and Development Directorate, Naka, Ibaraki (Japan)

Description

SS316L(N)-IG is the candidate material for the in-vessel and ex-vessel components of ITER (International Thermonuclear Experimental Reactor). This paper describes an examination into weldability of irradiated and un-irradiated SS316L(N)-IG for coolant piping and investigation of the mechanical properties of welding joints as well as the effect of helium generation on weldability. A YAG laser welding process was used for repair welding of the water cooling branch pipelines. It was clarified that welding of SS316L(N)-IG irradiated up to 0.3 dpa (He content: about 3 appm) can be carried out without a significant deterioration of tensile properties due to helium accumulation. Therefore, repair of coolant pipes for the ITER blanket can be performed by the laser welding process. (author)

Additional details

Publishing Information

Journal Title
FAPIG (Tokyo)
Journal Issue
no.173
Journal Page Range
p. 16-20
ISSN
0014-5645

Optional Information

Notes
13 refs., 8 figs., 1 tab.