Structural components design and analysis of side wall in a Korean HCCR TBM for ITER |
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| Affiliation: | 1. Korea Atomic Energy Research Institute, Daejeon, Republic of Korea;2. National Fusion Research Institute, Daejeon, Republic of Korea;1. Faculty of Engineering and Resource Science, Akita University, 1-1, Tegatagakuen-cho, Akita 010-8502, Japan;2. Fusion Research and Development Directorate, Japan Atomic Energy Agency, 2-166, Omotedate, Obuchi, Rokkasho, Kamikita, Aomori 039-3212, Japan;1. St Petersburg State Polytechnical University, 29 Polytechnicheskaya, 195251 St Petersburg, Russian Federation;2. Ioffe Physico-Technical Institute, 26 Polytechnicheskaya St., 194021 St Petersburg, Russian Federation;3. ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance, France;1. Graduate School of Science, Shizuoka University, Shizuoka, Japan;2. National Institute for Fusion Science, Gifu, Japan;3. Institute for Applied Mechanics, Kyushu University, Kasuga, Fukuoka, Japan;4. Graduate School of Engineering, Hokkaido University, Sapporo, Japan;5. Department of Material Science, Shimane University, Matsue, Shimane, Japan;6. Hydrogen Isotope Research Center, University of Toyama, Toyama, Japan;1. Karlsruhe Institute of Technology (KIT), Institute for Neutron Physics and Reactor Technology (INR), Germany;2. Karlsruhe Institute of Technology (KIT), Institute for Applied Materials (IAM-WPT), Germany;3. Indian Institute of Technology Madras (IITM), Department of Mechanical Engineering, India;1. Open Joint-Stock Company “N.A. Dollezhall Research and Development Institute of Power Engineering”, (OJSC “NIKIET”), 107140, Malaya Krasnoselskaya 2/8, Moscow, Russian Federation;2. D.V. Efremov Scientific Research Institute of Electrophysical Apparatus, 196641 St. Petersburg, Russian Federation |
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| Abstract: | Korea has developed a helium cooled ceramic reflector (HCCR) test blanket module (TBM) consisting of four sub-modules in an ITER. From the draft design of the side wall (SW) according to a thermal-hydraulic analysis, a mechanical analysis was performed considering a design channel pressure of 10 MPa. The SW comprised of sixteen grids with the seventeen partitions for the manifold function satisfied 1.5Sm of the allowable stress (Sm) according to RCC-MR code at the maximum stress region in the SW. In addition, an elastic analysis of the draft design of the back manifold (BM) was carried out, which supported the four sub-modules in the HCCR TBM and has the main inlet/outlet of the He cooling pipe, the measurement pipes, and He purge gas lines from the port cell. The results show that the maximum stress was higher than 1.5Sm, and the BM design has been modified to satisfy the BM function and requirements. |
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| Keywords: | Back manifold (BM) RCC-MR code Side wall (SW) Test blanket module (TBM) Tresca stress |
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