You need JavaScript to view this

Structural design of shield-integrated thin-wall vacuum vessel and manufacturing qualification tests for International Thermonuclear Experimental Reactor (ITER)

Abstract

Conceptual design of shield-integrated thin-wall vacuum vessel has been done for ITER (International Thermonuclear Experimental Reactor). The vacuum vessel concept is based on a thin-double-wall structure, which consists of inner and outer plates and rib stiffeners. Internal shielding structures, which provide neutron irradiation shielding to protect TF coils, are set up between the inner plate and the outer plate of the vessel to avoid complexity of machine systems such as supporting systems of blanket modules. The vacuum vessel is assembled/disassembled by remote handling, so that welding joints are chosen as on-site joint method from reliability of mechanical strength. From a view point of assembling TF coils, the vacuum vessel is separated at the side of port, and is divided into 32 segments similar to the ITER-CDA reference design. Separatrix sweeping coils are located in the vacuum vessel to reduce heat fluxes onto divertor plates. Here, the coil structure and attachment to the vacuum vessel have been investigated. A sectorized saddle-loop coil is available for assembling and disassembling the coil. To support electromagnetic loads on the coils, they are attached to the groove in the vacuum vessel by welding. Flexible multi-plate supporting structure (compression-type gravity support), which was designed during CDA,  More>>
Authors:
Shimizu, Katsusuke; Shibui, Masanao; Koizumi, Koichi; Kanamori, Naokazu; Nishio, Satoshi; Sasaki, Takashi; Tada, Eisuke [1] 
  1. Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan). Naka Fusion Research Establishment
Publication Date:
Sep 01, 1992
Product Type:
Technical Report
Report Number:
JAERI-M-92-135
Reference Number:
SCA: 700480; PA: JPN-93:001005; SN: 93000936350
Resource Relation:
Other Information: PBD: Sep 1992
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; VACUUM SYSTEMS; MECHANICAL STRUCTURES; ITER TOKAMAK; SHIELDING; ELECTRIC CONDUCTIVITY; COMPUTER-AIDED DESIGN; MECHANICAL TESTS; SPECIFICATIONS; MAGNET COILS; SUPPORTS; DYNAMIC LOADS; 700480; COMPONENT DEVELOPMENT; MATERIALS STUDIES
OSTI ID:
10123125
Research Organizations:
Japan Atomic Energy Research Inst., Tokyo (Japan)
Country of Origin:
Japan
Language:
Japanese
Other Identifying Numbers:
Other: ON: DE93764160; TRN: JP9301005
Availability:
OSTI; NTIS; INIS
Submitting Site:
JPN
Size:
149 p.
Announcement Date:
Jun 30, 2005

Citation Formats

Shimizu, Katsusuke, Shibui, Masanao, Koizumi, Koichi, Kanamori, Naokazu, Nishio, Satoshi, Sasaki, Takashi, and Tada, Eisuke. Structural design of shield-integrated thin-wall vacuum vessel and manufacturing qualification tests for International Thermonuclear Experimental Reactor (ITER). Japan: N. p., 1992. Web.
Shimizu, Katsusuke, Shibui, Masanao, Koizumi, Koichi, Kanamori, Naokazu, Nishio, Satoshi, Sasaki, Takashi, & Tada, Eisuke. Structural design of shield-integrated thin-wall vacuum vessel and manufacturing qualification tests for International Thermonuclear Experimental Reactor (ITER). Japan.
Shimizu, Katsusuke, Shibui, Masanao, Koizumi, Koichi, Kanamori, Naokazu, Nishio, Satoshi, Sasaki, Takashi, and Tada, Eisuke. 1992. "Structural design of shield-integrated thin-wall vacuum vessel and manufacturing qualification tests for International Thermonuclear Experimental Reactor (ITER)." Japan.
@misc{etde_10123125,
title = {Structural design of shield-integrated thin-wall vacuum vessel and manufacturing qualification tests for International Thermonuclear Experimental Reactor (ITER)}
author = {Shimizu, Katsusuke, Shibui, Masanao, Koizumi, Koichi, Kanamori, Naokazu, Nishio, Satoshi, Sasaki, Takashi, and Tada, Eisuke}
abstractNote = {Conceptual design of shield-integrated thin-wall vacuum vessel has been done for ITER (International Thermonuclear Experimental Reactor). The vacuum vessel concept is based on a thin-double-wall structure, which consists of inner and outer plates and rib stiffeners. Internal shielding structures, which provide neutron irradiation shielding to protect TF coils, are set up between the inner plate and the outer plate of the vessel to avoid complexity of machine systems such as supporting systems of blanket modules. The vacuum vessel is assembled/disassembled by remote handling, so that welding joints are chosen as on-site joint method from reliability of mechanical strength. From a view point of assembling TF coils, the vacuum vessel is separated at the side of port, and is divided into 32 segments similar to the ITER-CDA reference design. Separatrix sweeping coils are located in the vacuum vessel to reduce heat fluxes onto divertor plates. Here, the coil structure and attachment to the vacuum vessel have been investigated. A sectorized saddle-loop coil is available for assembling and disassembling the coil. To support electromagnetic loads on the coils, they are attached to the groove in the vacuum vessel by welding. Flexible multi-plate supporting structure (compression-type gravity support), which was designed during CDA, is optimized by investigating buckling and frequency response properties, and concept on manufacturing and fabrication of the gravity support are proposed. Partial model of the vacuum vessel is manufactured for trial, so that fundamental data on welding and fabrication are obtained. From mechanical property tests of weldment and partial models, mechanical intensity and behaviors of the weldment are obtained. Informations on FEM-modeling are obtained by comparing analysis results with experimental results. (author).}
place = {Japan}
year = {1992}
month = {Sep}
}