Overview of LLCB TBM design and R&D activities in India

• Published in: Fusion engineering and design Vol. 109-111; pp. 1522 - 1527
• Main Authors: Kumar, E. Rajendra, Vyas, K.N., Jayakumar, T.
• Format: Journal Article
• Language: English
• Published: Elsevier B.V 01.11.2016
• Subjects: Breeding blanket; DEMO; ITER; LLCB; TBM; ITER; Breeding blanket; LLCB; DEMO; TBM
• ISSN: 0920-3796; 1873-7196
• DOI: 10.1016/j.fusengdes.2015.11.038

The Lead-Lithium Ceramic Breeder Test Blanket Module (LLCB-TBM) is the Indian TBM representing the DEMO breeding blanket, to be installed in ITER radial port no-2 for testing in ITER. The conceptual design of LLCB TBM systems and their engineering design are under progress. The neutronic analysis and engineering design of LLCB TBM set (TBM+TBM Shield) is undergoing optimization. The LLCB TBS auxiliary systems; Helium cooling systems, Lead-Lithium Cooling System and Tritium Extraction Systems design are conceptualized and detail design is under progress. The system arrangements in port cell area, Tokamak Cooling Water System (TCWS) vault and Tritium building along with interface requirements have been worked out within the allocated space. LLCB TBS related R&D activities are under progress at Institute for Plasma Research (IPR), Gandhinagar in association with Bhabha Atomic Research Centre (BARC), Mumbai and Indira Gandhi Centre for Atomic Research, Kalpakkam. The major research and development areas are liquidmetal technologies, lithium ceramic pebbles, lead-lithium eutectic alloy, India specific Reduced Activation Ferritic Martensitic Steels (IN-RAFMS) development and fabrication technologies development. This paper will highlight the current LLCB TBM set and axillary systems design and status of R&D activities in various areas.