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Conceptual design of SC magnet system for ITER, (2). Stress analysis

Technical Report:

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  More>>
Authors:
Koizumi, Koichi; Hasegawa, Mitsuru; Yoshida, Kiyoshi [1] 
  1. Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan). Naka Fusion Research Establishment
Publication Date:
Aug 01, 1991
Product Type:
Technical Report
Report Number:
JAERI-M-91-121
Reference Number:
SCA: 700430; PA: JPN-91:011146; SN: 92000630562
Resource Relation:
Other Information: PBD: Aug 1991
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; ITER TOKAMAK; SUPERCONDUCTING MAGNETS; STRESS ANALYSIS; SOLENOIDS; FINITE ELEMENT METHOD; SUPPORTS; MAGNET COILS; THERMONUCLEAR REACTOR MATERIALS; 700430; MAGNET COILS AND FIELDS
OSTI ID:
10109006
Research Organizations:
Japan Atomic Energy Research Inst., Tokyo (Japan)
Country of Origin:
Japan
Language:
English
Other Identifying Numbers:
Other: ON: DE92750955; TRN: JP9111146
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
JPN
Size:
212 p.
Announcement Date:
Jun 30, 2005

Technical Report:

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}
}