Title of article :
Fracture mechanics analysis including the butt joint geometry for the superconducting conductor conduit of the National Centralized Tokamak
Author/Authors :
Takahashi، نويسنده , , Hiroyuki and Kudo، نويسنده , , Y. and Tsuchiya، نويسنده , , K. and Kizu، نويسنده , , K. and Ando، نويسنده , , T. and Matsukawa، نويسنده , , M. and Tamai، نويسنده , , H. and Miura، نويسنده , , Y.، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 2006
Pages :
7
From page :
1005
To page :
1011
Abstract :
This paper presents the dependence of the stress intensity factor on a geometrical factor estimated by fracture mechanics analysis around the defect in the butt joint weld of a cable-in-conduit conductor (CICC) of a superconducting coil. The stress intensity factor can be estimated by the Newman–Raju equation applied to the CICC section, but the effect of the difference between the geometry assumed in the equation and the actual CICC geometry has not been clarified yet. Therefore, the three-dimensional finite element method (3D-FEM) is performed to estimate the geometrical factor. As a result, the Newman–Raju equation is considered to be applicable for the assessment of the fracture toughness of the rectangular-shaped conduit because the maximum stress intensity factor by 3D-FEM is only 3% larger than that determined by the Newman–Raju equation for the maximum postulated defect.
Keywords :
National Centralized Tokamak , Newman–Raju equation , Butt joint weld , Fracture mechanics , Superconducting conductor , Stress intensity factor
Journal title :
Fusion Engineering and Design
Serial Year :
2006
Journal title :
Fusion Engineering and Design
Record number :
2352982
Link To Document :
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