Abstract
The International Thermonuclear Experimental Reactor (ITER) is an experimental tokamak machine testing the basic plasma performance and technologies required for future tokamak reactor. The design proposals for the Superconducting (SC) Magnet System from Japan were summarized by the Fusion Experimental Reactor (FER) Design Team and the Superconducting Magnet Laboratory of the Japan Atomic Energy Research Institute (JAERI). This report is one of the series reports on `Conceptual design of superconducting magnet system for ITER`, and describes the major results of the stress analysis regarding the Toroidal Field (TF) coil, the Center Solenoid (CS) coil and the Equilibrium Field (EF) coil and their support structures. Among the design issues, the mechanical design of the coil system was one of the most critical items, not only because of the huge electromagnetic loads due to large size and high magnetic field, but also because of the demand of high reliability under neutron irradiation. In order to satisfy both the coil performance and the mechanical reliability, different types of conductors were employed for each coils. The mechanical behaviors and the safety margin of each coil were analyzed by using finite element method (FEM) of MSC/NASTRAN. The procedure to obtain the equivalent winding stiffness employed
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Koizumi, Koichi;
Hasegawa, Mitsuru;
Yoshida, Kiyoshi
[1]
- Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan). Naka Fusion Research Establishment
Citation Formats
Koizumi, Koichi, Hasegawa, Mitsuru, and Yoshida, Kiyoshi.
Conceptual design of SC magnet system for ITER, (2). Stress analysis.
Japan: N. p.,
1991.
Web.
Koizumi, Koichi, Hasegawa, Mitsuru, & Yoshida, Kiyoshi.
Conceptual design of SC magnet system for ITER, (2). Stress analysis.
Japan.
Koizumi, Koichi, Hasegawa, Mitsuru, and Yoshida, Kiyoshi.
1991.
"Conceptual design of SC magnet system for ITER, (2). Stress analysis."
Japan.
@misc{etde_10109006,
title = {Conceptual design of SC magnet system for ITER, (2). Stress analysis}
author = {Koizumi, Koichi, Hasegawa, Mitsuru, and Yoshida, Kiyoshi}
abstractNote = {The International Thermonuclear Experimental Reactor (ITER) is an experimental tokamak machine testing the basic plasma performance and technologies required for future tokamak reactor. The design proposals for the Superconducting (SC) Magnet System from Japan were summarized by the Fusion Experimental Reactor (FER) Design Team and the Superconducting Magnet Laboratory of the Japan Atomic Energy Research Institute (JAERI). This report is one of the series reports on `Conceptual design of superconducting magnet system for ITER`, and describes the major results of the stress analysis regarding the Toroidal Field (TF) coil, the Center Solenoid (CS) coil and the Equilibrium Field (EF) coil and their support structures. Among the design issues, the mechanical design of the coil system was one of the most critical items, not only because of the huge electromagnetic loads due to large size and high magnetic field, but also because of the demand of high reliability under neutron irradiation. In order to satisfy both the coil performance and the mechanical reliability, different types of conductors were employed for each coils. The mechanical behaviors and the safety margin of each coil were analyzed by using finite element method (FEM) of MSC/NASTRAN. The procedure to obtain the equivalent winding stiffness employed for the each FEM analysis is also described in this report. The details on the coil specifications, conductor design and mechanical design for each coils are described in other report of the series reports. (J.P.N.).}
place = {Japan}
year = {1991}
month = {Aug}
}
title = {Conceptual design of SC magnet system for ITER, (2). Stress analysis}
author = {Koizumi, Koichi, Hasegawa, Mitsuru, and Yoshida, Kiyoshi}
abstractNote = {The International Thermonuclear Experimental Reactor (ITER) is an experimental tokamak machine testing the basic plasma performance and technologies required for future tokamak reactor. The design proposals for the Superconducting (SC) Magnet System from Japan were summarized by the Fusion Experimental Reactor (FER) Design Team and the Superconducting Magnet Laboratory of the Japan Atomic Energy Research Institute (JAERI). This report is one of the series reports on `Conceptual design of superconducting magnet system for ITER`, and describes the major results of the stress analysis regarding the Toroidal Field (TF) coil, the Center Solenoid (CS) coil and the Equilibrium Field (EF) coil and their support structures. Among the design issues, the mechanical design of the coil system was one of the most critical items, not only because of the huge electromagnetic loads due to large size and high magnetic field, but also because of the demand of high reliability under neutron irradiation. In order to satisfy both the coil performance and the mechanical reliability, different types of conductors were employed for each coils. The mechanical behaviors and the safety margin of each coil were analyzed by using finite element method (FEM) of MSC/NASTRAN. The procedure to obtain the equivalent winding stiffness employed for the each FEM analysis is also described in this report. The details on the coil specifications, conductor design and mechanical design for each coils are described in other report of the series reports. (J.P.N.).}
place = {Japan}
year = {1991}
month = {Aug}
}