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Author(s) |
Chaudhuri, P.; Ranjithkumar, S.; Sharma, D.; Danani, C.; Swami, H. L.; Bhattacharya, R.; Patel, A.; Kumar, E. R.; Vyas, K. N. (BARC)
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Source |
Fusion Engineering & Design, 2014. Vol. 89: pp. 1362-1369 |
ABSTRACT
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The Indian Lead–Lithium Ceramic Breeder (LLCB) Test Blanket Module (TBM) is the Indian DEMO relevantblanket module, as a part of the TBM program in ITER. The LLCB TBM will be tested from the first phaseof ITER operation in one-half of an ITER port no. 2. LLCB TBM-set consists of LLCB TBM module andshield block, which are attached with the help of attachment systems. This LLCB TBM set is inserted in awater-cooled stainless steel frame called ‘TBM frame’, which also provides the separation between theneighboring TBM-sets (Chinese TBM set) in port no. 2. In LLCB TBM, high-pressure helium gas is used tocool the first wall (FW) structure and lead–lithium eutectic (Pb–Li) flowing separately around the ceramicbreeder (CB) pebble bed to cool the TBM internals which are heated due to the volumetric neutron heatingduring 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 TBMset using ANSYS. This paper will also describe the performance analysis of individual components of LLCBTBM set and their different configurations to optimize their performances. |
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