Nuclear analysis and shielding optimisation in support of the ITER In-Vessel Viewing System design |
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| Affiliation: | 1. EURATOM/CCFE Fusion Association, Culham Science Centre, Abingdon, Oxon OX14 3DB, UK;2. F4E Fusion for Energy, Josep Pla 2, Torres Diagonal Litoral B3, 08019 Barcelona, Spain;3. ITER Organisation, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance, France;1. Max-Planck-Institute for Plasmaphysics, EURATOM Association, Garching, Germany;2. Institute for Measurement Systems and Sensor Technology, Technische Universität München, Germany;1. Université de Lyon, LTDS, UMR CNRS 5513 - ECL/ENISE, 58 rue Jean Parot, 42023 Saint-Etienne cedex 2, France;2. Valahia University of Targoviste, FIE/ICSTM, B-dul Unirii 18-20, 130082 Targoviste, Romania;1. State Key Laboratory of Structural Analysis for Industrial Equipment, School of Aeronautics and Astronautics, Dalian University of Technology, Dalian 116024, China;2. Shanghai Institute of Satellite Engineering, Shanghai 200240, China;3. National Laboratory of Space Intelligent Control, Beijing Institute of Control Engineering, Beijing 100080, 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 |
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| Abstract: | The In-Vessel Viewing System (IVVS) units proposed for ITER are deployed to perform in-vessel examination. During plasma operations, the IVVS is located beyond the vacuum vessel, with shielding blocks envisaged to protect components from neutron damage and reduce shutdown dose rate (SDR) levels. Analyses were conducted to determine the effectiveness of several shielding configurations. The neutron response of the system was assessed using global variance reduction techniques and a surface source, and shutdown dose rate calculations were undertaken using MCR2S.Unshielded, the absorbed dose to piezoelectric motors (PZT) was found to be below stable limits, however activation of the primary closure plate (PCP) was prohibitively high. A scenario with shielding blocks at probe level showed significantly reduced PCP contact dose rate, however still marginally exceeded port cell requirements. The addition of shielding blocks at the bioshield plug demonstrated PCP contact dose rates below project requirements. SDR levels in contact with the isolated IVVS cartridge were found to marginally exceed the hands-on maintenance limit. For engineering feasibility, shielding blocks at bioshield level are to be avoided, however the port cell SDR field requires further consideration. In addition, alternative low-activation steels are being considered for the IVVS cartridge. |
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| Keywords: | In-vessel viewing Shielding ITER Fusion |
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