Design of structural components for the helical reactor FFHR-d1A |
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| Affiliation: | 1. Department of Energy System Engineering, Seoul National University, Seoul, Republic of Korea;2. Center for Advance Research in Fusion Reactor Engineering, Seoul National University, Seoul, Republic of Korea;3. ITER Korea, National Fusion Research Institute, Daejeon, Republic of Korea;4. ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul-lez-Durance, France;1. Karlsruhe Institute of Technology, 76344, Karlsruhe, Germany;2. EURATOM/CCFE Fusion Association, Culham Science Centre Abingdon, Oxfordshire OX14 3DB, UK;1. CIEMAT, Avda. Complutense 40, 28040 Madrid, Spain;2. IDOM, Avda. Monasterio de El Escorial 4, 28049 Madrid, Spain;1. VTT Technical Research Centre of Finland, P.O. Box 1300, FI-33101 Tampere, Finland;2. Tampere University of Technology, Korkeakoulunkatu 6, 33720 Tampere, Finland;1. ENEA Brasimone, Camugnano, Bologna, Italy;2. Dipartimento di Energia, Ingegneria dell’Informazione e Modelli Matematici, Università di Palermo, Viale delle Scienze, Palermo, Italy;3. ENEA Bologna, Via Martiri di Monte Sole 4, Bologna, Italy |
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| Abstract: | FFHR-d1 is a conceptual design of the helical reactor being developed at the National Institute for Fusion Science. The maintenance of in-vessel components is very important for the fusion demo reactor. In addition, sufficient pathways are needed for the divertor exhaust. To implement these, the vacuum vessel, coil support structure, and cryostat require large apertures. However, the coil support structure has to be sufficiently rigid to remain within soundness and deformation limits. A design combining the structural components in the FFHR-d1A was developed from mechanical and thermal viewpoints. Consequently, components having a sufficiently large port area were provided. An investigation of the maintenance and exhaust schemes has been planned on the basis of this fundamental design. |
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| Keywords: | Helical Reactor design Superconducting magnet Vacuum vessel |
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