Engineering design and analysis of Indian LLCB TBM set

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• 作者：S. Ranjithkumar^a ; ^{ranjith@ipr.res.in" class="auth_mail" title="E-mail the corresponding author} ; Deepak Sharma^a ; Paritosh Chaudhuri^a ; Chandan Danani^a ; E. Rajendra Kumar^a ; Istiyak Khan^b ; Sujay Bhattacharya^b ; K.N. Vyas^b
• 关键词：ITER ; LLCB TBM ; Shield block ; Structural analysis ; ANSYS
• 刊名：Fusion Engineering and Design
• 出版年：2016
• 出版时间：1 November 2016
• 年：2016
• 卷：109-111
• 期：part_PB
• 页码：1581-1586
• 全文大小：2370 K

文摘

India is developing Lead Lithium cooled Ceramic Breeder (LLCB) Test Blanket Module (TBM) for testing in ITER for the validation of fusion blanket design tools, tritium breeding performance and high grade heat extraction capability relevant to Indian DEMO. LLCB TBM is designed to withstand various ITER loads and its combinations, like thermal, mechanical including the high pressure coolant loads, electromagnetic loads during plasma disruption and seismic loading conditions. LLCB TBM system is designed in compliance with ITER Safety requirements and guidelines. A few challenging part in the design includes the design of helium cooled First Wall (FW) and back plates, the attachment system between TBM and the shield block to withstand loads for all the ITER operational modes, routing of high temperature process pipes between TBM and the shield block, interfaces between process pipes and the connecting flange, design of manifolds of different process fluids etc. Analysis has been performed on the LLCB TBM set using a Finite Element code, ANSYS. Relevant codes and standards, namely the French code RCC-MR, has been followed for the design analysis. The details of the analysis and further plans and proposals for improvement in design will be discussed in this paper.