Concept design on RH maintenance of CFETR Tokamak reactor |
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| Affiliation: | 1. Institute of Plasma Physics, Chinese Academy of Sciences, Hefei, China;2. University of Science and Technology of China, Hefei, China;1. Fusion for Energy, Torres Diagonal Litoral B3, Josep Pla 2, 08019 Barcelona, Spain;2. ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul-lez-Durance, France;1. EURATOM/Culham Center Fusion Energy, Culham Science Centre, OX14 3DB, Abingdon, UK;2. EFDA Close Support Unit Garching, Boltzmannstaße 2, D-85748 Garching Bei München, Germany;3. Karlsruhe Institute of Technology, Institute for Neutron Physics and Reactor Technology, Hermann-von-Helmholtz-Platz 1, D-76344 Eggenstein-Leopoldshafen, Germany;4. Instituto de Fusión Nuclear/UPM, Madrid, Spain;5. VTT Technical Research Centre of Finland, P.O. Box 1000, FI-02044 VTT, Finland;6. Karlsruhe Institute of Technology, Institut für Fördertechnik und Logistiksysteme, Gotthard-Franz-Straße 8, Geb.50.38, 76131 Karlsruhe, Germany;1. EURATOM/CCFE Fusion Association, Culham Science Centre, Abingdon, Oxfordshire OX14 3DB, United Kingdom;2. EFDA Close Support Unit Garching, Boltzmannstaße 2, D-85748 Garching bei München, Germany;1. CEA, IRFM, F-13108 Saint-Paul-Lez-Durance, France;2. CAS, IPP, Hefei, Anhui, China;1. Institute of Plasma Physics, Chinese Academy of Sciences, Hefei 230031, China;2. University of Science and Technology of China, Hefei 230015, China |
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| Abstract: | CFETR which stands for Chinese Fusion Engineering Testing Reactor is a superconducting Tokamak device. The concept design on RH maintenance of CFETR has been done in the past year. It is known that, the RH maintenance is one of the most important parts for Tokamak reactor. The fusion power was designed as 50–200 MW and its duty cycle time (or burning time) was estimated as 30–50%. The center magnetic field strength on the TF magnet is 5.0 T, the maximum capacity of the volt seconds provided by center solenoid winding will be about 160 VS. The plasma current will be 10 MA and its major radius and minor radius is 5.7 m and 1.6 m respectively. All the components of CFETR which provide their basic functions must be maintained and inspected during the reactor lifetime. Thus, the remote handling (RH) maintenance system should be a key component, which must be detailedly designed during the concept design processing of CFETR, for the operation of reactor. The main design work for RH maintenance in this paper was carried out including the divertor RH system, the blanket RH system and the transfer cask system. What is more, the technical problems encountered in the design process will also be discussed. |
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| Keywords: | CFETR RH maintenance Concept design Tokamak |
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