Status of ITER TBM port plug conceptual design and analyses |
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| Affiliation: | 1. ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance, France;2. ENEA Frascati, Italy;3. University of Palermo, Italy;4. LTCalcoli, Piazza Prinetti 26/B, 23807 Merate, Italy;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. 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;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 |
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| Abstract: | The test blanket module port plug (TBM PP) consists of a TBM frame and two TBM-sets. However, at any time of the ITER operation, a TBM set can be replaced by a dummy TBM. The frame provides a standardized interface with the vacuum vessel (VV)/port structure and provides thermal isolation from the shield blanket. As one of the plasma-facing components, it shall withstand heat loads while at the same time provide adequate neutron shielding for the VV and magnet coils. The frame design shall provide a stable engineering solution to hold TBM-sets and also provide a mean for rapid remote handling replacement and refurbishment. This paper presents main design features of the conceptual design of TBM PP with two dummy TBMs. Also analysis results are summarized to evaluate shielding, hydraulic, and thermal and structural performances of the TBM PP design. |
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| Keywords: | ITER Tokamak Plasma facing components TBM port plug (TBM PP) |
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