Published November 1996 | Version v1
Journal article

Welding and cutting characteristics of blanket/first wall module to back plate for fusion experimental reactor

  • 1. Kawasaki Heavy Industries, Ltd., Kobe (Japan)

Description

The first wall and the blanket of the International Thermonuclear Experimental Reactor (ITER) are used under severe conditions such as the neutron irradiation by plasma, surface thermal load, the electromagnetic force at the time of plasma disruption and others. Consequently, from the viewpoint of the necessity for disassembling and maintenance, those are divided into modules in toroidal and poloidal directions. In this study, as to the welding of the back plate and the legs supporting blanket modules, which are installed in a vacuum vessel, the characteristic test paying attention to the deformation at the time of welding was carried out, and the optimal welding conditions and the characteristics of welding deformation and others were clarified. Moreover, when water jet method was used for cutting the welded parts of the supporting legs, the properties of the cut parts, the time for cutting and others were examined. The performance required for the welded parts of blanket modules with back plate is shown. The basic test of welding conditions using plate models, partial model test and whole model test are reported. The test of water jet cutting for the maintenance of shielding blanket modules is described. (K.I.)

Additional details

Publishing Information

Journal Title
FAPIG (Tokyo)
Journal Issue
no.144
Journal Page Range
p. 39-45.
ISSN
0014-5645
CODEN
FPIGAG