Progress in engineering design of Indian LLCB TBM set for testing in ITER |
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| Affiliation: | 1. Institute for Plasma Research, Bhat, Gandhinagar 382428, Gujarat, India;2. Bhabha Atomic Research Center, Mumbai 85, India;1. Technical University of Catalonia (UPC), Jordi Girona 1-3, 08034 Barcelona, Spain;2. Technology for Fusion (T4F) Research Group, GREENER, Department of Heat Engines, Spain;3. Technology for Fusion (T4F) Research Group, GREENER, Department of Physics and Nuclear Engineering, Spain;4. EURATOM-CIEMAT Association, 28040 Madrid, Spain;1. Scientific Technical Center SINTEZ, D.V. Efremov Institute, 196641 St. Petersburg, Russia;2. I.I. Polzunov Scientific & Development Association on Research and Design of Power Equipment, 191167 St. Petersburg, Russia;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. The University of Tokyo, Tokyo, Japan;2. Max-Planck-Institut für Plasmaphysik, EURATOM Association, Garching, Germany |
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| Abstract: | The Indian Lead–Lithium Ceramic Breeder (LLCB) Test Blanket Module (TBM) is the Indian DEMO relevant blanket module, as a part of the TBM program in ITER. The LLCB TBM will be tested from the first phase of ITER operation in one-half of an ITER port no. 2. LLCB TBM-set consists of LLCB TBM module and shield block, which are attached with the help of attachment systems. This LLCB TBM set is inserted in a water-cooled stainless steel frame called ‘TBM frame’, which also provides the separation between the neighboring TBM-sets (Chinese TBM set) in port no. 2. In LLCB TBM, high-pressure helium gas is used to cool the first wall (FW) structure and lead–lithium eutectic (Pb–Li) flowing separately around the ceramic breeder (CB) pebble bed to cool the TBM internals which are heated due to the volumetric neutron heating during plasma operation. Low-pressure helium is purged inside the CB zones to extract the bred tritium. Thermal-structural analyses have been performed independently on LLCB TBM and shield block for TBM set using ANSYS. This paper will also describe the performance analysis of individual components of LLCB TBM set and their different configurations to optimize their performances. |
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| Keywords: | ITER TBM LLCB Thermal-hydraulics First wall Shield block |
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