Alternatives of ITER vacuum vessel support system
Creators
- 1. Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan). Naka Fusion Research Establishment
Description
Optional designs of vacuum vessel (VV) support have been performed for the International Thermonuclear Experimental Reactor (ITER) to reduce stresses and buckling concern of the flexible plate structure in ITER-FDR. One of the optional designs is hanging type VV support concept that consists of top hanging supports at the top of VV and middle radial stoppers in the middle of outboard VV. The hanging supports are located at the toroidal field (TF) coil inboard top region (R∼5400 mm) using the narrow window space surrounded by a poloidal field coil (PF1) and TF coil. The radial stoppers are located inside TF coil cases in the TF coil outboard middle region (R∼9300 mm). The upper flange connection of the radial stoppers should slide in vertical direction to eliminate thermal stress produced by relative thermal displacement between VV wall and TF coil case. Both supports consist of flexible plates and are mounted on 18 locations in toroidal direction. The radial and toroidal reaction forces are shared with the hanging supports and the radial stoppers. However, the vertical force is sustained by only the hanging supports. The others are compressive type support concept that consists of nine VV supports located in alternate divertor port regions in toroidal direction. Two designs have been performed for the VV support concept. One is mounted on TF inter-coil structures (OIS) and the other is on cryostat ring. The compressive support on TF coil OIS is dependent on TF coil movement but that on cryostat is independent. In the optional designs, the bending stress due to the relative thermal displacement between TF coil and VV is classified to primary stress according to ASME Sec. III NF. The stress due to TF coil displacement is also considered as primary stress. The stress due to non-uniform temperature distribution of the flexible plate is classified to secondary stress. The preliminary structural assessments for the optional designs have been performed for all load combinations to confirm the structural feasibility. Three optional designs have enough structural integrity for all load combinations. The restriction of the hanging type support is that there is no space for port in upper region of VV and the upper shape of VV should be flattened and moved downward by 100 mm to attach the support flanges. The top Correction Coil (CC) radial spans need to be modified from the side edge to the center of the TF coil case. For the designs of the compressive type support, alternate divertor port should be eliminated in toroidal direction. (author)
Availability note (English)
Available from INIS in electronic form; Also available from JAEA; URL: http://jolisf.tokai-sc.jaea.go.jp/pdf/tec/JAERI-Tech-2002-053.pdfFiles
37002521.pdf
Files
(3.9 MB)
| Name | Size | Download all |
|---|---|---|
|
md5:6157e8334e7effb2e7fb7cf95c367ed6
|
3.9 MB | Preview Download |
Additional details
Publishing Information
- Imprint Pagination
- 96 p.
- Report number
- JAERI-Tech--2002-053
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 37002521
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- COMPUTER-AIDED DESIGN; CONTAINERS; FASTENERS; FLEXIBILITY; FRACTURE PROPERTIES; ITER TOKAMAK; MODULAR STRUCTURES; STRESS ANALYSIS; STRESSES; SUPPORTS; VACUUM SYSTEMS
- Descriptors DEC
- CLOSED PLASMA DEVICES; DESIGN; MECHANICAL PROPERTIES; MECHANICAL STRUCTURES; TENSILE PROPERTIES; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS
Optional Information
- Notes
- 13 refs., 22 figs., 48 tabs.; This record replaces 34022435